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LA-13631-T Thesis Approvedforpublicre/ease; distribution is unlimifed. Etching of L102in NF3 RF Plasma Glow Discharge Los Alamos NATIONAL LABORATORY LOSAlamos National Laboratoryis operated by the University of Cal#ornti for the United States Department of Energy under contract W-7405-ENG-36.

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Page 1: LosAlamos - International Atomic Energy Agency

LA-13631-TThesis

Approvedforpublicre/ease;distributionis unlimifed.

Etching of L102in

NF3 RF Plasma Glow Discharge

Los AlamosNATIONAL LABORATORY

LOSAlamos National Laboratory is operated by the University of Cal#orntifor the United States Departmentof Energy under contract W-7405-ENG-36.

Page 2: LosAlamos - International Atomic Energy Agency

.

This thesis was accepted by the Department of Philosophy Engineering,the Llniversity of New Mexico, Albuquerque, New Mexico, in partialfulfillment of the requirements for the degree of Doctor of Philosophy.The text and illustrations are the independent work of the author andonly the front matter has been edited by the CIC-1 Writing and EditingStaff to confbrm with Department of Energy and Los Alamos NationalLuboratoy publication policies.

An Aj5mtive Action/Equal Opportunity EmployeY

This report was prepared as an acmunt of work sponsored by an ageny of the llni~ed StatesGovernment. Neither The Regents @the University of (Mijornia, the United StatesGovernment nor any agency thereo~ nor any of their employees, makes any warranty, expressor implied, or assumes any legal liability or responsibility for the accuracy, completeness, orUs@lnffis of any information, apparatus,product, or process disclosed, orrepresents that itsuse would not infringe privately owned rights. Refmence herein to any specl$c commercialproduct, process, or sewice by trade name, trademark, manufacturer, or otherwise, does notnecessarily mtitute or imply its endorsement, recommendation, or favoring by The Regentsof the University of Cal~omia, the United States Government, or any ageney thereof. Theviews and opinions #authors expressed herein do not necessarily state or r@’ect those ofThe Regents of the University of Calfornia, the United States Government, or any agencythereo$ .?RSAlamos National Woratoy strongly supports academic freedom and aresearcher’s right to publish; as an institution, however, the .Laboratoy does not endorse theviewpoint of a publication or guarantee its technical correctness.

Page 3: LosAlamos - International Atomic Energy Agency

DISCLAIMER

Portions of this document may be i!legible

in electronic image products. Images are

produced from the best available original

document.

Page 4: LosAlamos - International Atomic Energy Agency

L4-13631-TThesis

Issued: August 1999

Eiching of L102 in

NF3 RF Plasma Glow Discharge

John M. Veilleux

Los AlamosNATIONAL LABORATORY

Los Alamos, New Mexico 87545

Page 5: LosAlamos - International Atomic Energy Agency
Page 6: LosAlamos - International Atomic Energy Agency

Acknowledgments

I wish to thank Dr. Mohamed S. E1-Genk, my University and doctoral

advisor, who guided me during a verytrying time in my life, and helped me keep

this vision of a doctorate in mind. Mr. f-lamed Saber provided many important

observations and modeling insights to help me through an understanding of the

plasma reactions. Dr. E. Phil Chamberlain, my mentor at the Los Alamos National

Laboratory, guided me through the experimentation phase of my research, and

helped me really understand the meaning of applying science principles to an

observable.

I thank also Dr. Carter Munson and Dr. David Curtis of the Los Alamos

National Laboratory, who provided the overall technical direction and funding for

this work, as well as Dr. John Fitzpatrick, who provided guidance on the

chemistry of the plasma work. Special thanks are also due to the Chemical,

Science, And Technology Division’s Environmental Science and Waste

Technology Group (CST-7) for their continued funding of this waste

decontamination research project.

I thank also Catherine Auckland for her encouragement and patience who

made the process of pursuing a Ph.D. bearable.

This work was supported by CST-7 and CST-I 1, Los Alamos National

Laboratory, under the GRA program and by the Waste-Management Education

& Research Consortium under contract DE-FC-04-90AL-63805 to the Institute for

Space and Nuclear Power Studies.

v

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Table of Contents

Acknowledgments .............................................................................................. v

Table of Contents ............................................................................................. vii

List of Figures .................................................................................................... ix

List of Tables ..................................................................................................... xi

Nomenclature...

.................................................................................................. X111

Abstract ............................................................................................................. xv

Chapter 1. Introduction ....................................................................................... 1

1.1. Previous Work on Radionuclide Etching .................................................... 11.2. Application of RF Glow Discharge for Waste Processing .......................... 21.3. Objectives of This Work .............................................................................21.4. Organization .............................................................................................. 3

Chapter 2. Background and Literature Search ................................................. 5

2.1.2.2.2.3.2.4.2.5.2.6.2.7.2.8.2.9.

Plasma Description .................................................................................... 5Plasma Models .......................................................................................... 6Major Species in the Bulk Plasma ............................................................. 7Transport of Reactive Species to a Surface ..............................................7Etch Concepts from Semiconductor Applications ...................................... 8Chemical Etching of U02 with F2 ............................................................... 9Uranium and Fluorine Chemistry and Thermodynamics .......................... 10Liquid Scintillation Counting (LSC) .......................................................... 10Analysis ................................................................................................... 11

Chapter 3. Experimental Setup ........................................................................ 14

3.1.3.2.3.3.3.4.3.5.3.6.3.7.3.8.3.9.

Plasma System ........................................................................................ 14Absorbed Power ...................................................................................... 18DC Sheath Voltage ..................................................................................22Pressure and Gas Flow ........................................................................... 23Stainless-Steel Planchettes ..................................................................... 26Sample Preparation ................................................................................. 27Liquid Scintillation Counter (LSC) ............................................................ 31Lower Limits of Detection ........................................................................ 37Activity Measurement of Plasma Processed Samples ............................. 39

vii

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3.10. Temperature Measurements ................................................................ 423.11. Uncertainty in Measurements .............................................................. 433.12. Glow Discharge Obsewations ..............................................................47

Chapter 4. Results ............................................................................................. 52

4.1. The Etching Process ................................................................................ 524.2. Effect of Absorbed Power ........................................................................ 534.3. Effect of Plasma Gas Pressure ............................................................... 584.4. U02 Etch Rates ....................................................................................... 62

Chapter 5. CHEMKIN ....................................................................*.... .............*.. 64

5.4.5.2.5.3.5.4.5.5.5.6.5.7.5.8.

CHEMKIN Description ............................................................................. 64The CSTR Approximation ........................................................................ 66Plasma Reactions in CHEMKIN .............................................................. 67Surface Reactions ................................................................................... 71Thermodynamic Constants ...................................................................... 73CHEMKIN Validation ............................................................................... 73CHEMKIN Predictions for the Present Experiments ................................ 79Limitations on the Use of CHEMKIN ........................................................ 84

Chapter 6. U02 Etching And Application To Plutonium ................................. 85

6.1. The Plasma Species ................................................................................ 856.2. Reaction Model ........................................................................................ 87

6.3. Thermodynamic Analysis of Surface Etch Reactions .............................. 89

6.4. Volatile Surface Species .......................................................................... 94

6.5. Applications to Pu02 ................................................................................ 96

Chapter 7. Summary And Conclusions ......................................................... 100

Chapter 8. Recommendations for Continued Work ..................................... 103

8.1. Experiments with Depleted U02 ............................................................ 1038.2. Recovery system ................................................................................... 1048.3. in-Situ Measurements ............................................................................ 1048.4. Pu & PU02 work ..................................................................................... 104

Appendices ..................................................................................................... 105

Appendix A.Appendix B.Appendix C.Appendix D.Appendix E.

Properties ................................................................................ 106Experimental Details ................................................................ 115Data ......................................................................................... 138CHEMKIN ................................................................................ 150Analysis ................................................................................... 158

REFERENCES .........................................................................●............ .......... 171

...Vlll

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List of Figures

Figure 1.Figure 2.Figure 3.Figure 4.Figure 5.Figure 6.Figure 7.Figure 8.Figure 9.Figure 10.Figure 11.Figure 12.Figure 13.Figure 14.Figure 15.Figure 16.Figure 17.Figure 18.Figure 19.Figure 20.Figure 21.Figure 22.Figure 23.Figure 24.Figure 25.Figure 26.Figure 27.Figure 28.Figure 29.Figure 30.Figure 31.Figure 32.Figure 33.Figure 34.Figure 35.Figure 36.Figure 37.Figure 38.Figure 39.Figure 40.Figure 41.Figure 42.Figure 43.

Transport of Plasma Species to the U02 Surface . ............................... 8RF Plasma Reactor& Recovery System ............................................ 16~lasma Test Chamberand Schematic of RF Antenna ....................... 16~lectrical Circuits . ............................................................................... 17Matching Network Power Equivalency. .............................................. 17~owered Electrode Voltage, No Plasma . ........................................... 20‘owered Electrode Voltage, With Plasma ..........................................2l4bsorbed Power vs NF3 Gas Flow Rate ............................................. 214bsorbed Plasma Power as Function of Transmitted Power. ............22Measured DC Sheath Voltage in Experiments . ................................ 23NF3 Gas Flow Rate in SCCM . .......................................................... 25Pressure Variation with Absorbed Power and Gas Flow. .................25Experimental Flow Rate vs. Manufacturer’s Correlation ................... 26Depleted Uranium Alpha Spectrum . .................................................29Uranyl Nitrate Hexahydrate Spectra by Liquid Scintillation. .............29Specification of Uranyl Nitrate Hexahydrate Solution. ...................... 30Liquid Scintillation Discriminator Setting ........................................... 35233UStandard Used To Calibrate the LSC Discriminator. ................35Alpha and Beta Detection Efficiencies. ............................................36Detection Efficiency Vs. Solution pH . ............................................... 36Lower Detection Limits. ....................................................................39Spectrum Analysis for Sample Count Rate . ..................................... 41Temperature Rise in Plasma Reactor . ............................................. 43Accuracy of the Measurements . .......................................................46Uncertainty in Measured Fraction of UOZ Etched .............................46Typical Plasma Operations. .............................................................47Glow Discharge Observations at 50 W Absorbed. ...........................48Fraction of U02 Etched in NF3 RF Plasma . ......................................53Power Effects on U02 Etching at 17 Pa . .......................................... 55Effect of Power on NR,~,Xat 17 Pa ................................................... 56Effect of Power on t at 17 Pa ........................................................... 56Power Effects on U02 Etching at 10.8 Pa ........................................57Power Effects on U02 Etching at 32.7 Pa ........................................ 57Power Effects on U02 Etching at 39.4 Pa ........................................ 58Pressure Effects on U02 Etching at 25 W ........................................ 59Pressure Effects on U02 Etching at 50 W ........................................6OPressure Effects on U02 Etching at 100 W ...................................... 60Pressure Effects on U02 Etching at 170 W .....................................6 IPressure Effects on U02 Etching . ....................................................6lInitial Etch Rate of U02 . ................................................................... 63Average Etch Rate at 17 Pa . ............................................................63Experimental Setup of Perrin et. al ................................................... 77Comparison of CHEMKIN with Si Etching Experiments. ..................78

ix

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Figure 44.Figure 45.Figure 46.Figure 47.Figure 48.Figure 49.

..........

Maximum Variation in Rate Coefficient . ........................................... 78CHEMKIN Neutral Species Predictions at 17.0 Pa. ......................... 82CHEMKIN Ion Predictions at 17.0 Pa ...............................................82CHEMKIN Pressure Predictions . ...................................................... 83CHEMKIN Sensitivity with Flow Rate ............................................... 83Gibbs Free Energy of Formation for Uranium Fluorides/Oxyfluorides........................................................................................................... 92

Figure 50. Gibbs Reaction Energy, GR, for U02 Etching . .................................. 93Figure 51. Gibbs Reaction Energy, GR, for U Etching . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93Figure 52. Vapor Pressure of UFX Compounds . ................................................ 95Figure 53. Average Etch Rate ~ of UOZ Compared with PuOZ. ....................... 97Figure 54. Vapor Pressure of PUFGand UFGCompared .................................... 99Figure 55. Plutonium Compound Gibbs Free Energy of Formation ................... 99Figure B-1. RF Antenna . ..................................................................................ll6Figure B-2. Plasma Reactor and Recovery System. ....................................... 117Figure B-3. Inlet and Reactor Conditions .........................................................l2lFigure B-4. Experimental & Manufacturer’s Flow Calibration Data .................. 124Figure B-5. Rotameter Gas Flow Calibration ................................................... 125Figure B-6. Recovery System Flow and Throughput Characteristics ..............129Figure B-7. Recovery System Pressure Differential & Conductance ...............130Figure B-8. Effect of RF Power on Reactor Pressure ...................................... 133Figure B-9. Rotameter Setting During Plasma Operation ................................ 135Figure B-1 O. Plasma Extinguishing Pressure .................................................. 136Figure B-11. Type of Flow in Plasma Chamber . ............................................... 137Figure D-1. Determining the HF Partial Pressure ............................................ 153Figure D-2. Comparison of Chemkin and Experiment ..................................... 153Figure E-1. NF2 and NF3 Geometrical Cross Sections .................................... 160Figure E-2. Cross Section Correlation .............................................................l6lFigure E-3. Ion Energy Dependence on Cross Section . .................................. 163Figure E-4. Reaction Sequence of F Atoms and UOZ. .................................... 170Figure E-5. Reaction Sequence of F Atoms and U Metal . ............................... 170

x

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List of Tables

Table 1.Table 2.Table 3.Table 4.Table 5.Table 6.Table 7.Table 8.Table 9.Table 10.Table 11.Table 12.Table 13.Table 14.Table 15.Table 16.Table 17.Table 18.Table 19.Table 20.Table 21.Table 22.Table 23.Table 24.Table 25.Table 26.Table 27.Table 28.

I,

1

I

Plasma Etch Modeling Mechanisms ................................................... 12Modeling Approaches .......................................................................... 13Characteristics of Plasma System ....................................................... 15VPPCorrelations with Pt,, Plasma Ignited. ............................................ 19Absorbed Power Correlation with Rotameter Setting, F (cm) .............. 20Planchetie Characteristics ...................................................................26Activity and Mass Parameters of Sample Solution ............................... 28Sample Specifications ......................................................................... 31Detection Limits of Depleted U02 Samples ......................................... 38

Measurement Uncertainties ............................................................... 45Equations and Related Error Functions .............................................49Plasma Observations ........................................................................5lU02 Plasma Processing Results at 17 Pa .........................................55Typical Output Parameters . ...............................................................65Species in NF3 Plasma . .....................................................................68Plasma Chemistry in CHEMKIN . ....................................................... 69Plasma Surface Reactions. ............................................................... 72Parameters of Perrin et. al. (1990) Experiments . .............................. 75CHEMKIN Species Consolidation. ....................................................75Perrin et. al. (1990) Experimental Data at 200 W .............................. 76CHEMKIN Parameters for the U02 Experiment . ............................... 79CHEMKIN Parameters at 17 Pa . .......................................................8OCalculated Mole Fractions of Plasma Species at 17 Pa . ................... 86Plasma Conditions at 17 Pa . ............................................................. 87Bonding Sites for Reaction with F Radicals . ......................................88Favorable Thermodynamic Reactions of U-O-F . ............................... 90Unfavorable Thermodynamic Reactions of U-O-F. ........................... 91SurFace Species Volatility Data. ........................................................96

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Table A-1. Physical Properties Of Select Compounds ................................... 108Table A-2. Thermodynamic Properties Of Select Species .............................. 110Table A-3. Enthalpy and Gibbs Energy of Reaction for F Atom Reactions with

Uranium Fluorides and Oxyfluorides ............. ............................................ 112Table A-4.Table A-5.Table B-1.Table B-2.Table B-3.Table C-1.Table D-1.Table D-2.Table D-3.Table D-4.

Composition Of Stainless Steel ..................................................... 113Nuclear Properties Of Select Isotopes ........................................... 114Characteristics Of Plasma System .................................................ll6Plasma System Parts List . ............................................................. 118Stainless Steel Type 304 Sample Substrates ................................ 119Depleted UOP Experimental Data ..................................................l4OExperimental Mole Fractions & Pressure .......................................l52CHEMKIN Predictions, ~, for Perrin’s Experiment ........................ 154CHEMKIN Parameters for UOP Etching Experiment ...................... 154CHEMKIN Predicted Mole Fractions at 17 Pa for UOP Etching

Experiments . ............................................................................................. 155Table E-1.Table E-2.Table E-3.Table E-4.Table E-5.Table E-6.Table E-7.

Parameters for Etch Rate Calculation ............................................l59Physical Data on Select Species ................................................... 160Plasma Sheath Thickness and Ion Energy . ................................... 162Calculated Mole Fractions of Plasma Species at 17 Pa. ...............163Detailed Calculations for NF3 Ion ...................................................l64Energy From U02 Reactions with F Atoms .................................... 166Vapor Pressure Correlation ............................................................ 167

xii

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Nomenclature

Symbol DefinitionA Activity (Bq); Specific activity (Bq/g) indicated by bar over A.Bc;

cddeEEAfFFOGGfGRHfHRJ

JOk

k~KckfKnKPLmMnNNA/v~NR,~aP

Pr%

Paa

Exponent of temperature, T, in Arrhenius kinetics relationship.Concentration (mol m-3).Alpha instrument count rate (counts/rein).Beta instrument count rate (counts per minute).Standard state concentration (1 mole/L)Dilution factor.Molecular diameter (m).Relative erro~ Electron chargeEnergy (J)Activation energy (kJ mol-f).Activity ratio of an isotope to the total activity.Flow rate (mol S-l).Inlet flow rate (mol s-l).Molar Production Rate (mol S-l).Gibbs free energy of formation (kJ moi-l).Gibbs free energy of reaction (kJ mol-f).Enthalpy of formation (kJ mol-l).Enthalpy of reaction (kJ mol-l).Etch rate (rein-l; ~m/min); Average etch rate indicated by bar over J.;Flux (m-z S-l)Initial etch rate (rein-l; pm/min).Boltzman’s Constant, 1.381x1 O-23 J K-l; Thermal Conductivity (Win-lK-l)

Reaction rate constant, (cnz3nzolecule~-1S-*, where n is the order of

the reaction.Backward (reverse) rate coefficient of a reaction.Equilibrium constant of a reaction with respect to concentration.Forward rate coefficient of a reaction.Knudsen number.Equilibrium constant of a reaction with respect to pressure.Thickness (m)Mass (kg).Molecular weight (g/mole).Number density (m-3)Number of atoms or molecules.Avogadro’s Number, 6.022xI 023 mol-l.Ratio of remaining to initial activity= (&-A)/AO.Asymptotic value of U02 activity fraction removed.Power absorbed (W).Pressure (Pa).Probability that a beta emission will be correctly counted inwindow.Probability that an alpha emission will be correctly countedalpha window .

...X111

the beta

in the

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Symbol Definition

P“ Standard state pressure (1 Bar= 1x1O’ Pa)Pt, Power, Transmitted (W).Q Heat (W)R Gas Constant (8.3144 J mol-l K-l); Radius of glow discharge volume

(m)Rmax Maximum radius of glow discharge volume, equal to 25 cm.r Molar Production Rate per Unit Volume (mol S-ls Sheath thickness (m)s Cross sections! area (m*)SCCM Standard cubic centimeter per minute, gas flow

pressure.t Time (s); plasma process time; counting time;T Temperature (K)

Velocity (m/s): Volume (m3)Vs Sheath Voltage (V)x Mole fraction

GreekSymbol Definition

m-3).

rate at standard

half-life.

Pso

Y

Pv

BetaElectron temperature (in units of volts)Characteristic Etch Time (rein)Enthalpy (kJ mol-l)CountsDensity (kg m-3)Mean free path (m)Debye Length (m)Number of moles; Ratio of absorbed to transmitted powefiEfficiency.Specific gravity (kg m-3)Standard deviation; Cross section (m*)Sticking coefficient for a gaslwface reactantTotal mean counts; true mean of sampleViscosity (Pa-s)

SubscriptsSymbol Definitionb Bohm velocityc Critical level (for detection); Chamber (of plasma reactor)CR Combined chamber and recovery systemsD Qualitative level (for detection)e Electrons -! Ions

j Species numberInitial conditions

; Quantitative levelR Recovery system

(for detection)

xiv

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ETCHING OF U02 IN NF3 RF PLASMA GLOW DISCHARGE

by

John M. Veilleux

Abstract

A series of room temperature, low pressure (10.8 to 40 Pa), low power (25

to 210 W) RF plasma glow discharge experiments with U02 were conducted to

demonstrate that plasma treatment is a viable method for decontaminating U02

from stainless steel substrates. Experiments were conducted using NF3 gas to

decontaminate depleted uranium dioxide from stainless-steel substrates.

Depleted U02 samples each containing 129.4 Bq were prepared from 100

microliter solutions of uranyi nitrate hexahydrate solution. The amorphous U02

in the samples had a relatively low density of 4.8 gm/cm3. Counting of the

depleted U02 on the substrate following plasma immersion was performed using

liquid scintillation counting with alpha/beta discrimination due to the presence of

confounding beta emitting daughter products, 2-h and 2~Pa. The alpha

emission peak from each sample was integrated using a gaussian and first order

polynomial fit to improve quantification. The uncertainties in the experimental

measurement of the etched material were estimated at about* 2Y0.

Results demonstrated that UOZ can be completely removed from

stainless-steel substrates after several minutes processing at under 200 W. At

180 W and 32.7 Pa gas pressure, over 99% of all U02 in the samples was

removed in just 17 minutes. The initial etch rate in the experiments ranged from

0.2 to 7.4 pm/min. Etching increased with the plasma absorbed power and feed

gas pressure in the range of 10.8 to 40 Pa. A different pressure effect on U02

etching was also noted below 50 W in which etching increased up to a maximum

pressure, -23 Pa, then decreased with further increases in pressure.

The U02 etching process was self-limiting as the etch rate decreased

exponentially with immersion time to the end point. The end point was defined in

xv

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this work as when either all detectable U02 in the test sample was removed or

the etch rate became zero with U02 only partially removed. At both low and high

pressure, and low power (C 50 W), blocking occurred in which the end point was

reached before all U02 in the samples was completely removed.

A computer simulation, CHEMKIN, was applied to predict the NF3 plasma

species in the experiments. The code was validated first by comparing its

predictions of the NF3 plasma species with mass spectroscopy etching

experiments of silicon. The code predictions were within + 5% of the measured

species concentrations. The code predictions of plasma species in the U02

experiments were only applicable at 17 Pa because the assumption in the code

of a perfectly mixed plasma reactor was not met in the experimental chamber

except at 17 Pa.

The F

diffusing from

atom radicals were identified as the primary etchant species,

the bulk plasma to the UOZ surface and reacting to form a volatile

UF6, which desorbed into the gas phase to be pumped away. Ions created in the

plasma were too low in concentration to have a major effect on etching, but can

enhance the etch rate by removing non-volatile reaction products blocking the

reaction of F with U02.. The composition of these non-volatile products were

determined based on thermodynamic analysis and the electronic structure of

uranium. Analysis identified possible non-volatile products as the uranium

fluorides, UF2.~, and certain uranium oxyfluorides U02F, U02F2, UOF3, and UOF4

which form over the U02 sutiace. Successive reactions between these products

and F atoms lead to the formation of UFG. The UFG has a vapor pressure of 24

kPa, well above the operating pressure at the gas temperature (-300 K) of the

plasma, and, as a consequence, desorbs into the gas phase. The other

intermediate fluorides and oxyfluorides are solids and remain on the surface,

eventually slowing or blocking the etch reaction as they accumulate. These

results explain why when power was too low, the etch reactions completely

stopped before all detectable U02 could be fully etched. This is because the

rate of formation of the non-volatile products was higher that the removal rate,

xvi

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allowing the accumulation of non-volatile products preventing diffusing F-atoms

to react with the U02, thus eventually slowing and blocking the reaction.

Comparison of U02 with previously measured PU02 etch rates showed

that the removal of U02 and PU02 were comparable and differences could be

accounted for by differences in experimental conditions. The chemistry and

reaction thermodynamics of U02 have many parallels to those of PU02, such as

similar vapor pressures at room temperature (24 vs. 14 kPa) and favorable

Gibbs free energy of formation of many species. These favorable parallels

suggest that similar kinetics will occur with PUOZ but that further experimentation

with PU02 etching should be continued over the power and pressure parameter

space.

xvii

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CHAPTER 1. INTRODUCTION

The cost of decontamination, treatment, long term storage, and

monitoring of transuranic’ (TRU) waste in the United States in 1997 dollars has

been estimated at over $28,000/m3, compared to $1 ,800/m3 for low level

radioactive waste (Allen and Iiazelton, 1984). The total TRU volume exceeded

250,000 m3 in 1991 (Kisieleski et. al, 1994). Transuranic waste is defined to be

waste containing any alpha emitter with an atomic number greater than 92, a

half-life over 20 years, and an activity of 3700 Bqlg or greater. Plutonium and

americium waste contaminated objects are examples of transuranic waste, and

plasma treatment of such waste streams include contaminated glove-boxes and

high-value metallic objects such as ion sources. Other exampies of plasma

treatment applications are for enriched uranium recovefy from the cladding of

spent nuciear fuel (Kim et. al., 1999). The cost and safety of treating these

contaminated objects are a significant incentive to reduce the quantity of this

waste. Possible options include treatment to reclassify transuranic waste to low

level waste; volume reduction; or better yet a total or partial removal of the waste

from the metal object and full recovery of the radionuclides for subsequent

recycling or disposal. Unlike mechanical scrubbing and water jet techniques, RF

plasma is more effective for removal and recove~ of trace radionuclides from

surface crevices, can be operated remotely, and provides a better margin of

safety for the operator.

1.1. Previous Work on Radionuclide Etching

Eariy experiments performed in 1991 demonstrated the etching of

plutonium and plutonium oxide in fluorine based CFd02 RF plasma (Martz et. al.,

1991 ). They demonstrated PU02 average etch rates of -0.03 ~m/min at 50 W

and 26.7 Pa, and showed that Pu metal etching rates are lower than PUOZ by a

factor of 5 to 10. Their data also included pressure effects on Pu etching in the

range from 13 to 80 Pa, but the data were too few and had too much scatter to

confidently predict the relationship. The authors noted that their gravimetric

1

Page 20: LosAlamos - International Atomic Energy Agency

technique for measurement of mass loss during plasma processing was prone to

considerable error. Their PUOZ sample surface area exposed to plasma, varying

between 16.9 to 3.48 m2/g, were not well enough characterized to predict etch

rates with confidence. The authors also noted that their gravimetric technique for

measurement of mass loss during plasma processing was prone to consideiabie

error. Therefore, there was a need to continue this work to better quantify the

usefulness and limitations of using RF plasma glow discharge as an effective

decontamination technique for transuranic waste.

1.2. Application of RF Glow Discharge for Waste Processing

in an NF3 RF glow discharge, electrons are created which follow the RF

oscillations and collide with neutral particles to cause ionization, dissociation,

and other reactions. The most important species for etching are the creation of

atomic F radicals from NFs by electron collision. The F atoms then diffuse to the

surface where they react and volatilize contaminants, such as UO*. The

volatilized contaminants diffuse into the chamber where they are subsequently

pumped away, thus cleaning the underlying metal structure. The plasma, a

“quasi-neutral gas”, is in a highly non-equilibrium condition with neutral particles

near room temperature (- 298 K) while the electrons are at significantly elevated

temperatures, -50,000 K. Because the ionization fraction is small, typically c

0.001 Yo, the temperature experienced by objects in the plasma is room

temperature, and hence heating effects are minimal. As a result, plasma

cleaning can be accomplished without destroying the object to be

decontaminated.

1.3. Objectives of This Work

In this work, a series of single effect RF giow discharge experiments were

conducted with NFs gas to provide data on the dependence of the depleted

uranium dioxide (lJO*) etch rate from stainless steel surfaces on the absorbed

power and pressure. The power and pressure values were varied one at a time

and the etch rates of LJ02 from stainless steel surfaces were measured as a

2

Page 21: LosAlamos - International Atomic Energy Agency

function of immersion time. UOZ was used because it avoided the potential

inflexibil”ky and safety issues associated with experimentation with plutonium,

Provided data on the decontamination of U02 waste, provided procedures on

measurement techniques dealing with very small quantities of material, and

provided information on the physics of the processes. Unlike CFd02 plasma feed

gas used in other experiments (Martz et. al., 1991; Ianno et. al., 1981) , NFs

feed gas was chosen for plasma etching because it dissociates 10 to 25 times

faster and eliminates the possibility of forming carbon residues in the chamber

and on the surface of the sample, blocking the etching process. Consequently,

the U02 and NFs plasma data developed in this study can be applied to the

design of future experiments with plutonium because of similarities in the

chemistry including: similar oxidation states, similar volatility of the metal

hexafluoride, similar enthalpy of formation and Gibbs free energy of the

intermediate fluorides/oxyfluorides.

In these experiments, data were collected on the average etch rate of UOZ

as a function of the plasma immersion time, absorbed power, and gas pressure

at 17 Pa, the baseline case, with additional experiments conducted to establish

trends at both lower {10.8 Pa) and higher (31-40 Pa) pressures. Comparison of

the initial and the remaining radioactivity

etched during a certain immersion time.

develop a transient, multi-species diffusion

etching of U02 in the present experiments.

of tJ02 gave the average quantity

These results were also used to

model (E1-Genk et. al., 1999) for the

1.4. Organization

The organization of this paper follows with a background and literature

search. This chapter contains a description of the plasma and presents a

summary of the literature describing the plasma species, transport of species to

a surface, etch concepts that were advanced from studies in the silicon industry,

the chemistry and thermodynamics of uranium compounds, liquid scintillation

techniques, and data analysis references.

3

Page 22: LosAlamos - International Atomic Energy Agency

Chapter 3 describes the experimental setup. This chapter summarizes

the plasma system and operating parameters, describes how the uranium oxide

samples were prepared and characterized, describes the methods for quantifying

the remaining U02 following plasma immersion, and describes observations

related to the plasma glow discharge.

Chapter 4, Results, describes the baseline case (17 Pa, 50 W) to explain

the parameters used. This is followed by detailed data describing the power and

pressure variations on the amount of U02 etched. Finally, the etch rates are

calculated as a function of power and pressure.

The chapter on CHEMK!N, Chapter 5, describes the simulation code used

to determine the plasma species and their quantity as a function of power. The

chapter begins with a description of the code and modeling assumptions, and

describes the plasma chemistry, the surface chemistry, and thermodynamics.

Before applying the results to the present experiments, a validation was

performed and the results are described. The validation effort led to some

changes in the plasma chemistry and these were applied to the present

experimental setup which are described. Because of the approximations in the

code, application to the present experiments were limited to 17 Pa.

Chapter 6, Discussion and Application to PUOZ discusses the results of

UOZ etching and applies these results to PU02 using parallels in the chemistry

and thermodynamics. The self-limiting etching process with U02 is described in

terms of the formation of non-volatile surface species which block the reaction.

The parallels in the chemistry and thermodynamics of PU02 are investigated.

Chapter 7 summarizes the dissertation and draws conclusions. Finally,

Chapter 8 contains recommendations for future work in U02 etching, describes

improvements needed with the recove~ system, and, describes applications for

Pu and PU02 etching investigations.

Page 23: LosAlamos - International Atomic Energy Agency

CHAPTER 2. BACKGROUND AND LITERATURE SEARCH

Plasma processing experimentation in the semiconductor industry has

contributed to significant advances in the knowledge of the plasma and surface

chemist~ of the processes. Applications in the area of waste treatment and

decontamination, especially for radioactive waste on metallic substrates, has

received some emphasis. The first application to plutonium etching was reported

in 1991 (Martz et. al., 1991) and led the Los Alamos National Laborato~ in 1996

to continue this investigation with uranium, the subject of these experiments.

This chapter begins with a background on plasmas, focusing on how these

concepts may be applied toward decontamination of radionuclide contaminated

metals. It summarizes the literature search conducted to identify some of the

key etching concepts, provide data on species in the plasma, transport of

species to the contaminated surface, and etching

2.1. Plasma Description

A plasma is a collection of ionized and

concepts.

neutral particles and electrons

which, on the average, are electrically neutral (Lieberman & Lichtenberg, 1994;

Manes and Flamm, 1989; Dendy, 1993). A typical 13.56 MHz radio-frequency

(RF) glow discharge plasma drives highly mobile electrons to collide with neutral

gas atoms and molecules, resulting in ionization and dissociation of a gas, such

as NFs. There are many reactions occurring among the atoms, molecular

fragments, ions, and radicals of a plasma including recombination, electron

attachment, bimolecular collisions, and excitation reactions.

these effects is the creation of positive ions, negative ions, and

some of which are strongly reactive in a fluorine bearing gas,

The sum of all

neutral pa*icles,

such as F atom

radicals. A typical materials processing RF glow discharge plasma is

characterized by low-pressure (-0.1 to 140 Pa); weakly ionized (- 0.00170 of

total gas concentration); and containing 1014 to 1019 electrons per m3 with

energies in the 1 to 10 eV range, corresponding to electron temperatures of

11,600 to 116,000 K. The much heavier neutral and ionic constituents of this

plasma, unable to respond to the fast RF oscillations, retain thermal energies of

5-

Page 24: LosAlamos - International Atomic Energy Agency

- 0.026 eV, and therefore are at, or near, room temperature, -300 K.

Therefore, the RF glow discharge plasma is a highly non-equilibriufi thermal

system. The neutral species diffuse to surfaces where they “~n deposit their

energy (- 0.026 eV or 2.5 kJ/mole), adsorb, and react. A plasma sheath is

created at the plasma/wall/and plasma/electrode inte~aces of a chamber

because the RF driven discharge plasma acts like an RF diode. The RF

oscillations lead to the creation of a positive space charge buildup of ions near

surfaces, because the ions are unable to follow the rapid RF oscillation. This

creates strong electric fields in the sheath, directed from the plasma toward the

wall. Associated with this field is an effective DC voltage drop in the sheath

which accelerates ions into a surface, where they can deposit their energy,

enhancing surface reactions. The negative ionic species formed in

electronegative gases (Kouznetsov et. al, f 996), such as NF3, are the result of

electron attachment reactions that do not contribute to etching directly. These

negative ions are reflected at the plasma sheath and generally remain in the bulk

plasma; however, they affect the sheath thickness, the electron distribution, and

the F-atom concentration in a complicated way, and hence affect the overall

etching. Because the side wail area of a chamber is typically much larger than

the electrode surface area, the sheath voltage at the powered electrode is much

greater than the sheath voltage at the grounded walls. For this reason, samples

to be etched are often mounted on the powered electrode to achieve the

maximum ion bombardment effects.

2.2. Plasma Models

Models or a modeling approach was needed to provide estimates of the

plasma species and their concentrations. Several models were examined, as

tabulated in Table 2, and most were developed in support of semiconductor

applications. The CHEMKIN model was chosen as a result of this investigation

(Chapter 5). The model has an

been done with NF3, extensive

model was readily available.

extensive chemical reaction set, some work has

documentation is available, and the simulation

6

Page 25: LosAlamos - International Atomic Energy Agency

2.3. Major Species In the Bulk Plasma

As suggested by the. above plasma introduction, tie plasma is a

complicated mixture of many species. Mass spectroscopy inv~stigation of NF3

plasma species were conducted by a number of investigators’ (Pernn et. al.,

1990; Reese and Dibeler, 1956; Konuma and Bauser, 1993; Lui et. al., 1992;

Greenberg and Verdeyen, 1985; Honda and Brandt, 1984; Beattie, 1975; and

Weiner et. al., 1992). A database of 163 NF~02 reaction mechanisms, including

rate constants and activation energies, is available in the literature in support of

CHEMKIN (Meeks et. al., 1997; Meeks and Shon, 1995). Reported species

include: electrons; neutral species: F, F2, N, N2, N2F2, N2F4, N3, NF, NF2, NF3;

positive ions: F+, F2+, N+, N2+, NF+, NF2+, NF3+, N2F+; and negative ions: F2-,

F-.

2.4. Transport of Reactive Species to a Surface

For etching to take place, reactive bulk plasma species must be

transported to the surface containing the matefial to be etched (Lieberman and

Lichtenberg, 1991). The transport mechanisms are diffusion of

(Bird, 1960) and acceleration of ions through the plasma sheath

The concepts associated with the transport of reactive species

neutral species

to the material.

to a surface is

shown in Figure 1. Plasma neutral species, such as the highly reactive F atom

radicals, diffuse to the substrate sutiace with typical thermal velocity, vDti, and

adsorb to the surface via Van De Waals forces (physisorption) and

chemisorption (Lieberrnan and Lichtenberg, 1994). Positive ionic species, such

as F+ and NF2+, are accelerated through the negative potential of the plasma

sheath and attain much larger velocities, vAcc, determined by the potential

difference of the sheath, the velocity of the ions at the plasma sheath edge

(Bohm velocity), and collisions in the sheath. At the surFace, the ionic species

are rapidly neutralized because of the excess electrons present at the surface.

The surface chemistry is determined by chemical kinetics and the concentrations

of the reactive adsorbed species (Fogler, 1992; Levenspiei,

species, primarily fluorine, react to form a volatile product,

7

1972). These

usually a metal

Page 26: LosAlamos - International Atomic Energy Agency

fluoride, which desorbs into the bulk plasma to be pumped away. Thus, a

volatile radioactive contaminant ca~ be removed from a surface, leaving the

metallic substrate free of activity. If the sheath voltage is great enough (typically

500 to 1000 V), sputtering by energetic ions can also occur, causing the removal

of non-volatile species.

PIASMA REGIONN%Nfi+,Nfi F,~, F, etc.

(=+)‘+’

PlasmaSheath

i

Figure 1. Transport of Plasma Species to the U02 Surface.

2.5. Etch Concepts from Semiconductor Applications

Several review articles are available on general etch mechanisms, but

these are generally associated with silicon etching. Particularly extensive

reviews were conducted by Winters and associates (Winters and Cobum, 1992;

Winters et. al., 1983; Winters and Coburn, 1985), by Flamm and associates

(Flamm et. al., 1981; Flamm et. al., 1983) and others (Mauer et. al., 1978;

Zalm, 1986). In addition, a process similar to the oxidation of metals was

advanced for the fluorination of a surface (Babanov et. al., 1989; Cabrera and

Mott, 1949). Table 1 summarizes the etch mechanisms based on this review.

8

Page 27: LosAlamos - International Atomic Energy Agency

The etch mechanisms are divided into two types: , spontaneous (isotropic)

etching, and ion bombardment (anisotropic) assisted etching. The former is

called spontaneous because it relies on diffusion of the reactants with

subsequent chemical reaction to fofi the volatile product. It is considered

isotropic since it shows no preferential direction to etching. The latter, ion

bombardment, includes effects of energetic ions accelerated across the plasma

sheath to react with surface contaminants. It is anisotropic since the preferred

etch direction is along the ion path and hence, normal to the sheath. While the

concepts of isotropic and anisotropic etching are important for semiconductor

processing, they are not too important in the actinide etching described here.

However, spontaneous etching is important in that it permits etching in regions

inaccessible to plasma ions, such as inside crevices and pipe interiors.

Unlike UOZ etching, Si and SiOz etching with fluorine was found to result

in a constant etch rate. This effect was obsemed in plasma silicon etching with

NF3 (Stenger and Akiki, 1986), CFdOz (Donnelly et. al., 1984), and XeFz (Cobum

and Winters, 1979) gases. In U02 etching, the etch rate decreases with time,

as described in Chapter 6.

2.6. Chemical Etching of U02 with Fz

Etching in chemical reactors using elemental fluorine is also possible but

at temperatures above 700 K yielding etch rates of 1.3 micrometer/minute

(Iwasaki, 1968; Sakurai, 1974; Sazhin and Jeapes, 1997). Further, using F2

instead of NF3 for etching UOZ poses significant safety issues because limits are

0.1 ppm versus 10 ppm; Fz is very toxic compared to NFs; and short term Fz

gas ingestion can lead to death while NFs does not (MSDS for Fz and NFs).

Consequently, if Fz etching were used in place of plasma etching, a containment

chamber or facility would have to be built and high heat would have to be applied

to the substrate or gas to achieve the desired etch rate.

9

Page 28: LosAlamos - International Atomic Energy Agency

2.7. Uranium and Fluorine Chemistry and Thermodynamics

One of the eariier studies of uranium (and plutonium) I

fluorine: was performed at high temperature in a chel

(Vandenbussche, 1964). These experiments determined the etch

of U02, U03, U30& UOZF2, and UF4 with molecular fluorine.

experimentaiists have examined the fluorination of UOZ with F and

UF6 and the intermediate uranium oxyfluorides (Iwasaki, 1968; !

Machiels and Olander, 1977; Galkin and Zuev, 1984; Sazhin and

Lyman and Holland, 1987; Labaton and Johnson, 1959; Beattie

1985; Yahata and Iwasaki, 1964; and Souter and Andrews, 1997).

One of the most extensive reviews of the actinide chemi

uranium and its compounds, was published

Volume II contains an extensive listing of

prima~ sources include: Alberty and Silbey,

and Mossman, 1980; Cacace et. al., 1995;

et. al. 1980; Lide, 1993; Mallard, 1997;

Shackelford et. al., 1994; Venugopal et. al.,

in 1986 (Katz et. al.

thermodynamic prop

1997; Antony et. al.,

Hildenbrand and La!

Pearson, 1958; f

1992; Wagman et. :

Walker et. al., 1989. Included are the physical properties of select

compounds; thermodynamic properties to include enthalpy ar

energy of formation; Gibbs energy of reaction for select reactions;

stainless-steel; and nuclear properties. The properties used in

tabulated in Appendix A.

There are a number of excellent reference works on fluo

including: Simmons, 1950; Hinz et. al., 1980 (Gmelin); Lloyd, ~9;

Skoinik, 1976; Rosner and Allendorf, 197fi; Chen et. al., 1977; :

Sadeghi, 1991.

2.8. Liquid Scintillation Counting (LSC)

Development of the techniques for quantification of smal

uranium (-1 0-5 kg) was an important part of this research. The shl

10

Page 29: LosAlamos - International Atomic Energy Agency

alpha particle (Friedlander and Kennedy, 1949) in U02 results in self-shielding,

preventing an accurate activity measurement in surface counting devices, and

was an important consideration in choosing LSC (Chapter 3). The literature had

considerable data on using LSC to quantify alpha emitters: Bower et. al., 1994;

Passo and Kessler, 1992; Avila et. al., 1992; Pujol and Sanchez-Cabeza, 1997;

and Pates et. al., 1966. Because the UOZ samples had in-grown beta emitters,

calculating the lower limit of detection (Currie, 1968; Pastemack and Harley,

t 971) provided a means of quantifying the limits of LSC detection.

2.9. Analysis

Analysis of data, including error estimation, curve fitting to data, data

integration and differentiation, and counting statistics were necessary in the

evaluation of the spectral results and quantification (Bevington, 1969; Karen,

1997).

11

Page 30: LosAlamos - International Atomic Energy Agency

Table 1. Plasma Etch Modeling Mechanisms.

Type Of Etching Mechanism

Spontaneous or Isotropic Reactiie Species FluxTo SurfaceEtching

. DissociationEnergy

. Promoteadsorption

Precursor States

. Chemisorption

* Physisorption

Successive Fluorination(Mauer et. al. 1978, Flamm &Donnely 1981)

Field-~lsted Mechanism (Winters et. al. 1983)

* Theory Of Oxidation(Cabrera & Mott, 1949)

. Reduced ActivationEnergy

. Place Exchange Mechanism

Ion BombardmentAssisted Chemically Enhanced PhysicalSputtering(Mauer et. al.,Etching(Anisotropic 1978)Etching)

Damage Induced Chemical Sputtering(Flamm and Donnely,1981)

Surface inhibitors(Flamm and Donnely, 1981)

Field-Assisted Mechanisms(Winters et. al., 1983; Zalm,1986)(also cakd chemicalsputtering)

12

Page 31: LosAlamos - International Atomic Energy Agency

Table 2. Modeling Approaches.

Reference CommentsBarone & Graves,1995.Carter et. al., 1994.

Coltrin, et. al., 1996

Economou & Alkire,1988.

Kopalidis& Jome,1993

Martisovits&Zahoran, 1997

Meeks & Shon,1995.

Meeks et a!., 1997.

Moffat et. al., q991

Park & Economou,1991.

Shell, 1997.

Zawaideh & Kim,1987.

MolecularDynamicsSimulation.

MoiecularDynamicsSimulation.

Describesmethodology& equations used in Surface Chemkin. Does notconsiderionacceleration-only diffusing species.

Transportmodelwith diffusion& ion transport in a plug flow reactor.

Transportmodelwith diffusion& ion transport,one dimensional in parallelplate configuration.

Model for transportof neutral species. Transport of charged particlestosurfacesand their effects are not treated.

DevelopsCHEMKIN for use in plasma modelingwithetching. Determinesrate constantsvia solutionsto Boltzman equation. Gives Arrheniusfitstogas phase reactions. Develops governing equations, includingthesurface& plasma chemistry. No ion bombardmentmodeling.

Chemkin NF~02 plasma modeling for Si. Includesextensive chemisttyinthe plasmaalong with rate coeticients.

Continuouslystirredtank reactor approximationfor solvingkinetics&chemicalreactionsat surface. Uses surface Chemkin. No ionacceleration.

Transportmodelwith diffusion,no ion transport Parallel plate radialflowreactor.

Monte Carlo Simulation.Examines abstractive & dissociativeadsorptionwithvariousswfaca kineticsincluding surface diffusion,ad-layerordering,and weakly bound physiosorbed precursorstates.

Transport& Poissonequation solution that includesmost of theprocessesin plasma etching: physical sputtering,chemical etching,

,

enhanced physicalsputtering,enhanced chemical etching.

13

Page 32: LosAlamos - International Atomic Energy Agency

CHAPTER 3. EXPERIMENT SETUP

This chapter describes the experimental setup. Included; are the

descriptions of the plasma system, the method for determining the absorbed

power and sheath voltage, the NFs gas flow rate and resulting plasma pressure,

preparation and specification of the uranium oxide samples, the method

developed for achieving reproducible activity measurements of plasma

processed samples, and quantification of the uncertainty in the resulting

measurements. The chapter is concluded with a description of the visual

observations of the plasma during sample processing.

3.1. Plasma System

Experiments were

(Figure 2) with NFs gas

performed using a 13.56 M1-lz RF plasma system

to decontaminate depleted UOZ from the surface of

stainless-steel substrates. The system includes a vacuum chamber for

processing the samples and a fume hood mounted recove~ system for pumping

the chamber during processing. A power supply, matching network, and

electrical circuitry complete the system. Characteristics of the plasma system,

including room and fume hood flow rates, are summarized in Table 3. A detailed

equipment list and drawing of the plasma system is included in Appendix A.

A cubic (- 0.5 m per side) aluminum plasma chamber (Figure 3) with a

total internal volume of O.125-m3 and an internal surface area of 1.623 m2 was

used to process depleted uranium oxide samples in plasma. The RF powered

electrode surface area on which the UOZ samples were mounted measured

0.00203 m2. The volume and surface area were determined by measuring the

dimensions of all internal chamber and protuberances to the nearest centimeter.

A 6.5” x 0.5” thick quartz window provides an internal view of the plasma,

powered electrode, and sample. Details of the RF antenna are also depicted. A

5.08 cm diameter tray was mounted on the antenna holder and the 1.007 cm

diameter stainless steel U02 sample planchettes were placed on the 5.08 cm

14

Page 33: LosAlamos - International Atomic Energy Agency

tray. Under normal conditions, each plasma run was made with two U02

samples in the event one was lost due to experimental error or problems.

An attached fume hood mounted recovery system was used for pumping

the gas out of the chamber during plasma immersion experiments. Its total

volume, 0.0071 m3, was measured by expanding a known quantity of gas from

the plasma chamber. The recovery system was also designed to capture an

effluent radioactive gas by condensation in a liquid nitrogen cold trap, but this

feature was not used in the current experiments. A charcoal trap prevents pump

oil from back-streaming to the chamber and captures toxic gases created in the

plasma, such as F2, preventing escape to the environment. The final trap is the

pump oil itself, which captures any remaining uranium hexafluoride that gets

through the charcoal trap.

An RF20 power supply provides line, or transmitted power up to 2000 W,

an adjustable locally designed water-cooled matching network is used to

maintain zero reflected power during experiments, and a step-down voltage

divider with RF choke is used to measure the effective DC sheath voltage (Figure

4). Earlier experiments utilized a Zenith matching network and transmitted power

corrections were applied to normalize the data to the 1000W matching network.

This correction was done by equating the sheath voltage at varying transmitted

power at 50 cm gas flow rotameter setting and 17 Pa pressure (Figure 5).

Consequently, transmitted power values with the Heathkit matching network

were divided by 0.836 to make them equivalent to the 1000W matching network.

Table 3. Characteristics of Plasma System

Processing Chamber (Internal)Volume 0.125 m$Surface Area 1.623 m’

Recovery System Volume 0.0071 3

Powered Electrode Surface Area 0.00203 ~’

15

Page 34: LosAlamos - International Atomic Energy Agency

Plasma Chamber Recovery System

n13.56Mhzsupply aMatchingNetwork

nE!PiSam Ie

1, Ii

A EI JI-QxJ

1- Coid Trap Finger2- Charcoal Trap e3- Cold Trap Isolation Valves

Figure 2. RF Plasma Reactor& Recovery System.

ToRecoveryS@sm

SarOrneter

4

47 ●

[G “

f–w

49

Hei#lt47cm I

I\To NF3GasSu$ply

9;5

1

>

~~.n.ew % (b) SchematicofTest Chamber Rotsmetsr RF PlasmaAntenna(Wall-Anode) AllDimensions in centimeter (Cathode)

Figure 3. Plasma Test Chamber and Schematic of RF Antenna

Page 35: LosAlamos - International Atomic Energy Agency

RF-

4’L:’*’@DCvoltage

Dier

13.S6MHz

RF20 Plasma

PIasrnaEauivaleriI&wit

In out

IIRF Matchii t+awork DCVottagaDivider

EitherAHeathl&SA20600r tiFoHow+ng Cimuil

5 Turns.4- Da

‘“C” =“

Figure 4. Electrical Circuits.

---mu

100

Ptr.l+?athkii= 0.836*P@,,mw ~ Ii/

=/y--

I I

1t_\/d AAID / — I

I II III/ /6” i

Conditions

#/ /50 cm flow, 17 Pa

o0 50 100 150

RF-20 Transmitted Power, Pt, (W)

Figure 5. Matching Network Power Equivalency.

17

Page 36: LosAlamos - International Atomic Energy Agency

3.2. Absorbed Power

The power absorbed by the plasma was determined by a subtractive

power procedure (Horwitz, 1983; Godyak & Piejak, 1990) to eliminate the

necessity of measuring the voltage-current phase angle which would” have

required extremely precise and difficult measurements.

In the method, the peak-to-peak voltage at the RF antenna was measured

with and without a plasma. With no gas flow and chamber pressure of -0.5 Pa,

there was no plasma when RF power was applied. With these conditions, all

power losses occur in the matching network and lines. Next, a plasma was

initiated by flowing NFs gas and measuring the peak-to-peak voltage after the

chamber pressure had stabilized and with the reflected power adjusted to zero.

The power loss in this case is the sum of the matching network, lines, and

plasma losses. By comparing power with and without plasma at the identical

peak-to-peak voltage, the power absorbed by the plasma is the difference in

transmitted power with plasma and without plasma.

The antenna peak-to-peak voltage was measured with a Tektronix model

2225, 50 MHz oscilloscope coupled to a 1000:1 voltage divider between the

antenna and ground. The voltage divider used was similar to the one shown in

Figure 4 except that the choke was short circuited and the resistors were

replaced with a 10M series and 10K parallel resistor for a 1000:1 voltage

reduction. The first measurements without plasma were made with RF power

varying from zero to 550W. The antenna peak-to-peak RF voltage without

plasma is shown in Figure 6 and a least squares curve fit through the

experimental data points gives transmitted power as a function of the peak-to-

peak RF voltage (see figure for correlation). Next, measurements with a plasma

were taken of the antenna peak-to-peak voltage as a function of RF transmitted

power between 20 and 550 W at varying NF3 gas flow rates, based on the

Omega model S04-N082-03 rotameter settings of 20, 30,50, 80 and 100 cm. At

each gas flow and power setting, the reflected power was adjusted for a zero

value, and the peak-to-peak RF voltage measured after the pressure had

18

Page 37: LosAlamos - International Atomic Energy Agency

stabilized. Figure 7 shows the results of this experiment and the coefficients of

the least squares cuwe fits that relate the powered electrode peak-to-peak

voltage and transmitted power are tabulated in Table 4.

The absorbed plasma power, P, is then calculated at equal peak-to-peak

voltages as:

(1)

VPP is the antenna peak-to-peak voltage calculated with a plasma as

determined from the correlations shown in Figure 7 and Table 4. Next, the

transmitted power without plasma is calculated from the correlations shown in

Figure 6 using the values of VPPjust calculated. The results of this calculation

are shown in Figure 8, and the coefficients of the least squares curve fit through

the data are tabulated in Table 5. These correlations were then used to

determine the absorbed power from the transmitted power in the experimental

data.

Table 4. VPPCorrelations with Pti, Plasma Ignited.

Rotameter Coefficient of Coeilicient of ConstaSetting Pt: Ptr nt

( ) a, (VW_*) b, (V W-l)fro -5.284 5.92180 -3.586 5.005 689.350 -2.975x1 0-3 4.895 696.730 -2.878x1 0-3 5.155 655.020 -3.480x103 5.708 589.3

A secondary correlation for fraction of power absorbed, q, defined as the

ratio of absorbed, P, to transmitted, P@,power, was determined as a function of

transmitted power and pressure (Figure 9). This correlation was found to be

useful in providing an estimate of the absorbed power. The transmitted power

varies slowly with pressure and a least squares fit (inseit, Figure 9) gives the

pressure term in equation (2). From a physical view, the data suggests that as

transmitted power increases, fewer molecules are avaiiable to absorb the power,

so the ratio decreases. As the transmitted power decreases below - 100 W,

19

Page 38: LosAlamos - International Atomic Energy Agency

insufficient power is available for ionization and dissociation, and consequently

the power ratio drops.

~=;=o.42/l-~-]+tr(l.oo~lo-5P3-l.89~(2)

. L -1

Table 5. Absorbed Power Correlation with Rotameter Setting, F (cm)

P,, (W) Coefficient of FZ Coefficient of F Constant-..a, (W cm-2) b, (W cm-l) c, (w)

500 -0.008209 2.008 132.7400 -0.01031 1.776 103.7240 -0.005567 0.7583 78.37120 +8.828x104 -0.1203 53.45100 +().001812 -0.2354 46.8272 +0.003006 -0.3796 35.1550 +0.003624 -0.4511 25.56

No Plasma

600 v

400 ‘

200 “

Pf, = 5.376E-5 V; - 0.009878 VPP

o~no 1000 2000 3000 4000

Antenna Peak-Peak Voltage, VPP (V)

Figure 6. Powered Electrode Voltage, No Plasma.

20

Page 39: LosAlamos - International Atomic Energy Agency

3000

2000

1000

0

300

200

100

0

With Pfasma

Vw = ap~+bpr + c

See text for coefficients

o 200 400 600

Transmitted RF Power, P& (W)

Figure 7. Powered Electrode Voltage, With Plasma.

20 40 60 80 100 120

NF~ Flow Setting, F (cm)

Figure 8. Absorbed Power vs NF3 Gas Flow Rate.

21

Page 40: LosAlamos - International Atomic Energy Agency

:1■

&-‘--Q-—-—.—-—-—-—-

40 E~--

=; +3------------ ----- -----:-//_————_ ———— —. ——.

~ g?1

Q !

30 -

20 -

10 -

j’”FEEm_‘g

1

m

o 10.8

❑ 27.031.0

: 35.4■ 39.4Pa

- Jv

- -

* Praaaum Correlation

- -

-w m m *-1

nt1 I Preaaure, p(Pa)11 t I I i

“o 100 200 300 400 500

Transmitted Power, Ptr (W)

Figure 9. Absorbed Plasma Power as Function of Transmitted Power.

3.3. DC Sheath Voltage

During the experiments, absorbed power varied from 25 to 210 W and

resulted in DC equivalent sheath voltages ranging from 0.1 to 500 V,

respectively. Figure 10 shows that the sheath voltage depends on pressure;

the higher the pressure at constant power, the lower the sheath voltage.

The sheath voltage was measured across both sheaths (the powered

electrode sheath and the ground sheath) and the plasma (Figure 4). The voltage

drop across an RF plasma is quite small and thus the total voltage drop is

approximated as that due to the sheaths (Lieberman and Lichtenberg, 1994, p.

333). Because the areas of the powered eiectrode, S, in the experimental

system is 20.3 cm2 and that of the grounded wall is f 6025 cm2, the sheath

voltages will be highly asymmetric, with most of the voltage drop occurring on the

powered electrode according to equation (3) (Lieberman and Litchtenberg, 1994,

p. 370). For example, at 50 W absorbed power and 17 Pa, the measured voltage

is –142 V. Based on equation (3), the voltage across the grounded wail

22

Page 41: LosAlamos - International Atomic Energy Agency

becomes negligibly small, 8x1 0+ V. Therefore, the sheath voltage can be

assumed to be across the powered eleatrode sheath.

o

-1oo~

>*ci- -200

g5>c -300

z

2u)

-400

-500

$(3)

tbsorbed Power

Iw

24 ■

39

m

100#

168

210 ❑

10 20 30 40

Pressure, p (Pa)

Figure 10. Measured DC Sheath Voltage in Experiments.

3.4. Pressure and Gas Flow

For the conditions of these experiments, the NFs gas flow rate was

operated between 3 and 18.5 SCCM, resulting in plasma gas pressures varying

between 10.8 to 40 Pa, respectively, using the recove~ system vacuum

forepump. The following paragraphs describe the flow and pressure in the

system under varying power settings.

Pressure was controlled by adjusting the inlet gas flow indication, in

centimeter, using a rotameter, Omega model S04-N082-03. Manufacturer’s flow

23

Page 42: LosAlamos - International Atomic Energy Agency

correlation (Omega, 1995) with pressure was used to determine the gas flow rate

in standard cubic centimeter per minute (SCCM), which is the flow rate

converted to standard conditions at To, = 298 K and pO = one atmosphere

pressure (STP). The true flow rate of gas, in SCCM, is determined from the

manufacturer’s flow rate for air at STP, (SCCMh, the specific gravity of the gas

relative to air, ps (2.46 for NFs), the gas temperature, T, and the gas pressure, p,

in the chamber. With the gas temperature - 298K, the temperature dependence

cancels and the true flow depends directly on the square root of the pressure as

shown by Equation (4). The true flow rate in SCCM for NFs gas flow is shown in

Figure 11.

J(Scckf)o = ~, T p,—— (4)SC(34 TOp’ “

The chamber pressure varied with absorbed power and rotameter setting,

as shown in Figure 12. As power was appiied, the pressure increased aimost

instantaneousiy from the base pressure, reflecting the dissociation of NFs

moiecuies and an increase in totai number of moles of gas. This data was used

to determine the approximate flow meter setting to achieve a desired pressure.

The rotameter is an instrument designed to set flow conditions, rather

than to measure the actuai flow rate, and that is the manner it was used in these

experiments. Care was taken to set the flow conditions identically for aii

experiments. This inciuded verifyhg that the reguiated outiet pressure was 20

psig and that aii the vaives between the gas suppiy and the vacuum chamber,

except the rotameter adjustment valve, were fuiiy open. in order to verify the

volumetric gas flow, experiments were conducted (Appendix B) to determine the

true flow. The manufacturer’s correlations were found to reflect the true flow

rates over most of the range of pressures used, except at rota meter flow settings

above -90 cm, for which the manufacturer’s flow rates were understated (Figure

13).

24

Page 43: LosAlamos - International Atomic Energy Agency

NF~ Gas25

20

15

10

5

\(

40

30

20

10

0

Omega Model S04-N082-03T=298K

Rotameter SettingF=150cm

ggz=:80

50

30

20

10

Figure 11. NF~

20 30 40

Pressure, p (Pa)

Gas Flow Rate in SCCM.

< Solid lines are least squares fit throughthe experimental data.

v v. w 30v v v v

mv

n 20c1 u n

Rotameter Model: S04-N082-03

o 50 100 150 200 250

RF Absorbed Power, P (W)

Figure 12. Pressure Variation with Absorbed Power and Gas Flow.

25

Page 44: LosAlamos - International Atomic Energy Agency

0.0025

0.0020

0.0015

0.0010

0.0005

00 50

50

40

30

20

10

n

30co

Rotameter Flow Setting, F (cm)

Figure 13. Experimental Flow Rate vs.

Stainless-Steel Planchettes

Manufacturer’s Correlation.

A total of 12 stainless steel planchettes were machined from stock 304

material. Each planchette was measured with a vernier caliper and weighted

prior to first use. The characteristics are shown in Table 6, where the

uncertainties

planchettes.

are the standard deviations of the measurements from the 12

Detailed specifications are included in Appendix B.

Table 6. Planchette Characteristics

Characteristics Value

Mass (g) 0.5373 & 0.0019

Internal Diameter (cm) 1.007.+ 0.002

internal Depth (cm) 0.146 t 0.006

internal Surface Area (cm*) 0.796 ~ 0.(303

26

Page 45: LosAlamos - International Atomic Energy Agency

3.6. Sample Preparation

Depleted U02 in test samples were prepared by heating and flaming

solutions of uranyl nitrate hexahydrate pipetted in 100 PI increments into

cylindrically shaped 1.007-cm diameter stainless steel planchettes. The

following paragraphs describe the preparation and specification of the samples,

including the planchettes.

The depleted

U02(NQ~.6H20, was

uranyi nitrate hexahydrate, chemical formula

prepared in a 1M HN03 solution. To determine the atom

ratio of the various alpha emitting species in the solution, a small quantity was

diluted by a factor of 100:~ and electroplated onto a one-inch diameter stainless

steel wafer. Dilution and electroplating was necessary to achieve a uniformly

thin layer on the wafer that would yield a resolved spectrum. The alpha energy

spectrum, Figure 14, verified that the main alpha emitting isotopic components of

this solution were 23%, 2%, and a trace amount of 235U. These results were

obtained by counting the electroplated sample for 4000 minutes in a silicon solid

state alpha spectrum analyzer with multichannel analyzer and data multiplexer

connected to a DEC VAX computer. Table 7 summarizes the activity and atom

(or mass) ratios. The activity ratios, fj, j = 2%, 235U,and 2%J, were obtained by

first subtracting the background from the overall energy spectrum, summing the

counts under each of the three peaks (238U,235U, and 2%J) to obtain the total

counts, then taking the ratios of counts under each peak to the total counts. The

mass ratios were calculated by taking the ratio of the product of the activity ratio

and the half-life of the isotope to the sum of the products as shown in equation

(5):

(mass_ ratio), =fi(L,2)J

Zfi(h),

,j =B8 U,235U,~3 U. (5)

J

Liquid scintillation spectra of the uranyl nitrate alpha and beta emissions

alpha channelsare shown in Figure 15. The alpha spectrum was taken from the

27

Page 46: LosAlamos - International Atomic Energy Agency

while the beta spectrum was taken from the beta channels of the Packard 2550

counter. Comparing the observed spectra with a spectral atlas (Cross et. al.,

1983), the beta spectrum in this solution was attributed to the -h and 2MPa(m)

daughters of *MU. The emission peak in the beta spectrum near channel 245

was attributed to mislabeling of alpha emissions as beta in the counter. it should

be noted that the alpha emission energy peak in liquid scintillation counting is

\ower by a factor of at least 10 from the tme peak energy because the light

scintillation from the cocktail is measured rather than the alpha energy itself

(Passo and Kessler, 1992). As an example for calculating the instrument alpha

count rate, the liquid scintillation alpha peak for all uranium isotopes was

integrated using the procedures described in paragraph 3.9 and divided by the

count time to give the count rate. The count rate was then corrected for

alphalbeta misidentification, equation (15), and the activity calculated using

equation (16). The beta activity was calculated by integrating the beta spectrum

over the entire energy range (O to 2000 keV) except that alpha/beta corrections

were not applied, primarily because beta quantification was not needed in the

analysis.

Varying the volume of uranyl nitrate solution from 10 to 100 pi, counting

the alpha and beta emissions by liquid scintillation, and taking the slope of the

resultant curve provided the activity per unit volume of solution shown in Figure

16 and summarized in Table 7.

Table 7. Activity and Mass Parameters of Sample Solution

Isotope Activity Ratio, f Mass RatioSpecific Activity

(Ba/ul\To#al U 1.000 1.00000 1.294

u 0.895 0.99949 1.158:5U 0.102 0.00001 0.132

0.003 0.00050 0.0042~#, 2wPa (Beta) NA NA 2.153

28

Page 47: LosAlamos - International Atomic Energy Agency

Depleted Uranium a-Spectrum

% Count Time: 4000 Minutes150 ‘

100 ‘

50 -

235\

u*

234u

4.0 4.2 4.4 4.6 4.8 5.0

Energy (MeV)

Figure 14. Depleted Uranium Alpha Spectrum.

6000

4000

2000

0

Figure

.

1

II

Packard Model 2550TFUAB with CJPDiscrimination

o 150 300 450

Channel Number

fl5. Uranyl Nitrate Hexahydrate Spectra by Liquid Scintillation.

29

Page 48: LosAlamos - International Atomic Energy Agency

250

200

150

100

50

0

I

I !kdeted Uranvl Nitrate Hexalwdrate SoIution~ = 1.294* 0.020 Bq/@ ‘

I

A = 1.158 f 0.017 Bq/pl

A~ 2.153 f 0.042 Bq/wl

o 20 40 60 80 100

Volume (~1)

Figure 16. Specification of Uranyl Nitrate Hexahydrate Solution.

From the specifications in Table 7, the molar and mass conce

the solution can be determined. Let ~U be the specific activity t

uranium content (= 1.294 Bq/pi), j the isotope, fj the activity ratio of

total U, mj the mass of isotope j, Mj the molecular weight of j, ~j the m

the number of atoms or molecules containing j, NA Avogadro’s nun

volume of uranyl nitrate in the sample, and \ the half-life of j. Becal

the mass is due to 238U (0.99949), then the total number

total mass, m, is approximately equal to the mass of 238U.

of uranium to a compound, the mass of the compound is

of moles,

To conve

the mass

times the ratio of their molecular weights. The results are tabulated in

N, 2“ Vfjtl~,=~=~=

J~ NA 121(2)‘

~=~~, ‘~238U*

J

30

Page 49: LosAlamos - International Atomic Energy Agency

xm= mjZmn8u, (8)J

(9)

In preparing the samples for these experiments, 100 y] of uranyl nitrate

solution was pipetted onto a planchetie, heated on a hot plate to dryness, then

flamed until the stainless steel planchette turned red hot. The deposited U@

generally contained extensive voids, evident when viewed under a 200x

microscope. The density of the deposited material was calculated by filling one

stainless steel planchette with concentrated uranyl nitrate solution, prepared by

evaporating 20 ml of the original solution to near dryness. The planchette was

re-characterized because plasma processing during the course of these

experiments changed the depth and mass. With each 100 @ pipetted into the

planchette, the solution was converted to amorphous U02 by drying then flaming

the sample. In the final step, the UOZ in the sample was overfilled then filed to

make the UQ flush with the planchette’s top edge. The resulting amorphous

UOZ was weighted and its mass divided by the volume to determine its density.

The calculated density, with voids, was 4800 * 600 kg/m3 (Table 8).

Table 8. Sample Specifications

Parameter Value

Solution, UOZ(N03)2.6HZ0Molar Concentration of U (mol/L) 0.39 * 0.02Mass Concentration of U (g/L) 93.1 A 3.6

UOZ from 100 PI of SolutionDensity, p (kg/m3) 4800 ~ 600Mass, m (kg) 1.06 X 10”5Number of Molecules. N 2.36 X 1019

3.7. Liquid Scintillation Counter [LSC)

The original approach for determining the amount of radionuclides

removed following plasma processing was a gravirnetric technique of weighing

dried uranyl nitrate solution before and after processing. This approach was

unsatisfactory because the hydroscopic dry uranyl nitrate prevented accurate

31

Page 50: LosAlamos - International Atomic Energy Agency

and reproducible mass measurements, which did not significantly improve when

the uranyl nitrate was first converted to U02. The next method tried was simple

alpha counting of the surface of deposited U02, but alpha patilcie self-shielding

(Friedlander, 1949) prevented accurate measurement of the total activity of

samples. Liquid scintillation counting was therefore implemented in the present

experiments for alpha counting of the UOZ test samples (Passo and Kessler,

1992; Bower et. al., 1994).

The depleted uranium samples had significant beta activity as a result of

the ingrown daughter products of thorium and protactinium. As long as sufficient

quantities of uranium alpha emitters were in the sample, the beta activity could

be differentiated from the alpha activity. However, as the plasma etched away

the uranium (and any other volatile metal) leaving behind a significant portion of

the non-voiatiie metals, especially the beta emitting 2~h and 2wPa, beta activity

became a significant fraction of the total activity, preventing accurate counting or

even detetilon of the underlying alpha activity. Consequently, beta and alpha

discrimination was essential for quantifying uranium samples having appreciable

beta emitters when the alpha activity was comparatively small. The choice was

to remove the confounding beta emitters from the sample, or to utilize an

instrument capable of differentiating alpha from beta emitters. The choice was

the Packard Model 2550TFUAB liquid scintillation counter (LSC) for the

measurements, primarily because the daughters would have grown back during

the course of the experiments.

Liquid scintillation counters work on the principle of exchange of

radioactive particle kinetic energy to a fluor molecule in a liquid scintillation

cocktail, such as UitimaGoldw AB. The fluor molecule is activated to an

unstable higher energy state from which it is subsequently de-excited with the

emission of a photon. Since the radioactive material is surrounded by the fluor,

the liquid scintillation counter is a 47cdetection system. The photon impinging on

the photornultiplier tube is detected as a signal pulse. Electronic coincidence

circuits are included to minimize noise activated pulses. Alpha particles are

32

Page 51: LosAlamos - International Atomic Energy Agency

typically detected with near 100% eficiency while higher energy beta particles,

such as the beta isotopes in these samples, are detected with 95% efficiency.

I The 1009’o efficiency for alpha particles is achieved because they “have a

significantly greater energy transfer per unit distan6e traveled than do beta

particles. However, this effect also results in the loss of alpha particle energy

resolution and they appear as a single broad spectral peak at approximately one

tenth of their true energy—that is, in the hundreds of keV. This is the basis of all

liquid scintillation devices used for alpha quantifkation (Passo and Kessler,

1992).

The liquid scintillation counter, Packard Model 2550TFUAB, incorporates a

multichannel analyzer with a pulse decay analysis (PDA) circuit for differentiating

between alpha and beta particle generated light pulses originating from the

phosphor in the liquid scintillation cocktail. The design of the PDA uses the fact

that light scintillation originating from beta particles have a much shorter lifetime

than those emanating from alpha particles. To use this feature, the alphalbeta

discriminator level must be adjusted to minimize the misidentification of the two

particles.

Figure 17 shows the results of setting the discriminator level to minimize

the misidentification of alpha and beta emissions. The ideal setting was 115

giving an misidentification error of 2%. To generate this curve, a Iocaily prepared

pure uranium alpha emitter consisting of only 233Uand ‘*U uranyl nitrate in a 1.0

M nitric acid solution with a specific alpha activity of 2.977 Bq/microliter

determined from the LSC spectrum was used to generate the alpha counts as a

function of discriminator setting (Figure 18). The beta activity was less than

0.0058 Bq/microliter, indicating that most beta emitters were removed during the

preparation process. A Packard 14C beta emitter standard containing 2150 Bq

on 2/1/93 was used for the beta counts as a function of discriminator setting.

Activity correction for time elapsed since the solutions were standardized was not

necessary because the half-life is several thousand years. The counter’s alpha

33

Page 52: LosAlamos - International Atomic Energy Agency

and beta detection efficiencies (Figure 19) at a discriminator setthg of 115 were

determined to be 100% and 95.5%, respectively.

Quenching, or loss of counting efficiency with variation of the pH of the

uranyl nitrate solution, was an important parameter because of the desire’ to

prevent the solution from precipitating and to maximize the quantity of the

sample used for counting accuracy (Pulol and Sanchez-Cabeza, 1997). Nine

samples each consisting of 100 microliters of uranyl nitrate solution were dried

and the precipitate dissolved in nitric acid of varying molarity (0.01, 0.05, 0.1 and

0.2 M). Each sample’s pH was measured with an Orion model 920A pH meter

calibrated with buffers per manufacturer’s specifications. A 6 ml aliquot of

solution was then added to 14 ml of lJltimaGold AB cocktail and counted for 60

minutes. The resulting activity was compared to the expected activity to

determine the efficiency, taking into account the aliquot size and dilution factor.

The resulting activity versus pH is shown in Figure 20. The alpha counter

efficiency remained near 100% in the pH range 1.0 to 2.0, dropping significantly

for pH less than 1.0. Beta particle quenching increased with pH, but since the

prima~ interest was in alpha quantification, this effect had no impact on these

experiments. Above pH -2.5, precipitation of the uranyl nitrate in the cocktail

can occur, resulting in significant loss of counts.

34

Page 53: LosAlamos - International Atomic Energy Agency

80

60

40

20

0

t

Discriminator 115Error 2°A

t 1 I

3Packard Model 2550 TFUAB

.=. ‘. =.❑,

\ \ \ x“

Beta ‘ “n,

Mislabeled ‘\\\

1‘bndards:

14Cfor Beta

t 2% for Alphat

\\\

‘n,II

/

/\\\\\\

/

9V11GIEUG11GU\\\n 1

t “=1.0’ i-----n-LJ , n. n n I

o 50 100 150 200

Alpha/Beta Discriminator

Figure 17. Liquid Scintillation Discriminator Setting.

10000 \ I

. . . 120untTime: 300 min I

1000

100

10

1

Lti(.J4

=:

232 0u

i nil 1 INU,\Lli t 12.5 5.0 7.5

Energy (MeV)

Figure 18. 2% Standard Used To Calibrate the LSC Discriminator.

35

J

Page 54: LosAlamos - International Atomic Energy Agency

100

80

60

40

200

100

90

nw

n n mb

Alpha +3 ----R ?

r“/ I \

//

Beta,’,el

//

Packard Model2550 TFVAB

50 100 150

Alpha/Beta Discriminator

Figure 19. Alpha and Beta Detection Efficiencies.

200

r la. 1 6 ?

o

“B’. $ 0 0\ o 0 Alpha-..

13--..n-.-

•1 -----13 -n

Beta

0

I I I

Packard Model 2550 TR/AB

UltimaGoldm AB Cocktail80

‘1.0 1.5 2.0

Uranyl Nitrate Solution PI-I

Figure 20. Detection Efficiency Vs. Solution pH.

36

Page 55: LosAlamos - International Atomic Energy Agency

3.8. Lower Limits of Detection

Lower limits of detection were quantified for the Packard liquid scintillation

counter with the uranyl nitrate solutions because the interfering beta emitters

could confound the measurements. Detection limits were evaluated based on

three increasingly stringent detection levels: the critical level of detection, ~;

the qualitative level of detection, Ao; and the quantitative level of detection, ~

(Currie, 1968) and assuming that type I and II errors were both equal at 5%. A

type I error is the probability that radioactivity is obsewed when in fact it isn’t

present while a type II error is the probability of not obsetiing radioactivity when

in fact it exits. The critical level identifies the ability to detect the presence of a

signal, a binafy decision. The qualitative level identifies the ability to quantify the

signal with the specified value of the type !1 error. The quantitative level

identifies the ability to detect and to measure the signal with a high degree of

confidence.

Consider the case of a “blank” sample consisting only of background

radiation and interfering nuclides. The total mean counts from the blank, W, is

given by the sum of the mean counts from the background, W, and the

interfering nuclides, ~. The mean counts from the background were measured

using an LSC vial containing 6 ml of de-ionized water in 14 ml of Packard

UitimaGoldm AB liquid scintillation cocktail. The average alpha emissions taken

over three separate measurements of 60 minutes each was 0.1015

counts/second. The mean counts from the interfering nuclides were the beta

emitters from 2~h and 2%Pa daughters of 2mU that appeared in the alpha

window of the liquid scintillation counter (i.e., the mislabeled beta activity). The

total counts from this source, assuming that these emitters were not etched away

during plasma processing, is given by:

37

Page 56: LosAlamos - International Atomic Energy Agency

{n the above equation, px (2%) is the probability that a beta decay will

appear in the alpha window of the LSC, qP (0.955) is the counter eficiency for

beta activity, AP (2.153 Bq/pl) is ~he specific atiivity of beta emitte~ (Figure 16),

V (100 @) is the volume of the depleted uranyl n“-te in the sample before

plasma processing, and t is the instrument count time, typically 60 minutes. The

three activity limits of detection, with the alpha detection efficiency, q. -1.0, are

given by

Ac=~&,

AD = #.71 + 4.65A],

A,=;{l+[l+fi]}.

(12)

(13)

(14)

The activity for lower limits of detection for the Packard model 2550

TR/AB for the uranyl nitrate samples used in these experiments are plotted in

Figure 21 and the detection limits with 60 minutes count time is summarized in

Table 9. in the experimental results, the quantity of interest is NR, the ratio of

activity removed to the initial activity of the sample, 129.4 Bq. Thus, the LSC can

detect up to the hl~ limit, or 1 – A/l 29.4. For example, at the critical level, the

minimum detection level is 0.08 Bq. The equivalent UOZ etched ratio that can be

detected, ~R, is 0.99938. Consequently, the Packard model 2550 TR/AB liquid

scintillation counter can be used to detect the removal of all but 0.00062 fraction

of the initial U02.

Table 9. Detection Limits of Depleted UOZ Samples

Criteria Activity NR Limit(Ba)

Critical 0.08 0.99938Qualitative 0.16 0.99876Quantitative 0.50 0.99614

38

Page 57: LosAlamos - International Atomic Energy Agency

10

1

0.1

0.01

Packard Model 2550 TR/AB

A~

t

o 50 100 150 200

Counting time (Nlin)

Figure 21. Lower Detection Limits.

3.9. Activity Measurement of Plasma Processed Samples

Quantification of the samples’ activity following plasma immersion was

performed by first dissolving the plasma processed UOZ in hot 3M HNOS. The

surface activity of the pfanchette following this procedure was at or ~below

background.

To keep the solution pH in the range between 1.0 and 1.5 for LSC

counting, the 3M solution was evaporated to dryness and then dissolved in 0.05

M nitric acid before adding the solution to a LSC cocktaiL This had the effect of

keeping the pH in a narrow band above 1 but below 1.5. Several samples over

several weeks of data taking were verified to be in this range using pH paper.

With this procedure, it was possible to count all the dissolved uranium rather

than taking aliquot fraction of solution, thereby reducing the dilution factor from

-40 to 1 and significantly reducing the error from this source. Typical volumes

added to the liquid scintillation vials included - 6 ml of solution with 14 ml of

39

Page 58: LosAlamos - International Atomic Energy Agency

UltimaGold AB cocktail. Deionized distilled water was used for makeup volume

,. as needed to keep the total liquid scintillation volume at 20 ml.

All solutions were counted in LSC and the resulting spectrum was

integrated over the alpha peak to obtain the raw counts per minute. Figure 22

shows a typical alpha spectrum from a sample processed in plasma for 255

minutes at a power of 49.6 W absorbed and 17.3 Pa. The first peak is from the

beta activity that falls within the alpha window. The second peak is due to alpha

emissions. The procedure developed was to fit a gaussian and a first order

polynomial to the region of the cume that includes the entire alpha peak

(Bevington, 1969). From the least squares fit, the parameters of the gaussian

were plotted and the resulting cuwe integrated to give the total counts under the

gaussian peak, hence under the alpha peak. In the example shown, the counts

were 46483 yielding a count rate of 775 counts per minute (cpm). A program,

EasyPlot (Karen, 1997), was used to perform the cuwe fit and integration. This

procedure removed both the activity contribution from the beta emitters and the

background. For comparison, the LSC reported count rate using fixed energy

windows (channels 100 to 400) was 1211 cpm, which would have resulted in a

significant error.

40

Page 59: LosAlamos - International Atomic Energy Agency

600

400

200

0

255 rein, 49.6W, 17.3 Pa -

- LSC Spectrum Data

o 150 300 450

Channel, x

Figure 22. Spectrum Analysis for Sample Count Rate.

The raw counts obtained from LSC were next corrected for alpha and beta

mislabeling. The following terms apply C= the alpha count rate determined by

the gaussian fit, Cp the background corrected beta count rate reported by LSC

summed over all channels, pab the probability that an alpha emission appears in

the beta window, and pPa the probability that a beta emission appears in the

alpha window. The two latter probabilities are 0.02 in the present experiments.

Therefore, pap = 1- pwand PM = 1- pp~.The correction becomes:

C = C= + P.pc. - P#fXc/l =c=(2-pJ-cJh-Pbb). (15) ‘

To calculate the activity, A, from the count rate, C, requires corrections for

the dilution factor, d, and the alpha instrument efficiency, q= (-t). The dilution

factor in all later experiments was -1 because all the solution was included in the

LSC measurement. Earlier experiments were based on aliquots of the solution,

measured either volumetrically or gravimetricaily. The volumetric procedure

used ratios of volumes of original solution to the aiiquot for comparison, resulting

41

Page 60: LosAlamos - International Atomic Energy Agency

in d -40 along w“th significant errors. The resulting activity was calculated from

the relationship:

A=C~. (16)??a

The activity of uranium removed from the substrate surface normalized to

the initial activity, ~R, is defined from the activity obtained from equation (16) and

the initial activity of the UOZ sample before plasma processing, A., of 129.4 Bq

from Table 3, on

NR=l-~.4

3.10. Temperature Measurements

(17)

The temperature rise inside the plasma was monitored for a few cases, all

at 17 Pa and 50W absorbed power. These measurements were made at the

completion of plasma processing with power off and the system brought up to

atmospheric pressure via a nitrogen gas purge. The purpose was to verify that

the temperature during plasma processing remained near room temperature.

The measurements were made with an Omega l-fH81 meter with a type K

Inconel overbraided ceramic fiber insulated thermocouple, Omega model XCIB-

K-2-2. The bead welded exposed junction helped assure that temperature

rapidly reached equilibrium. Measurements were made of the ambient gas at

the center of the reactor, on the surface of the powered electrode, and on the

interior of the aluminum reactor wall. Ali measurements were made within -5

minutes of shutdown. Temperature comparisons with the ambient temperature

outside the reactor are shown in Figure 23. The wall and interior air temperature

rise was less than -5 K, while the temperature of the powered electrode rose 30

to 45 K, depending on the plasma immersion time. These results confirm that

the temperature inside the plasma remain near room temperature during plasma

processing although the temperature of the samples rise about 30-45 K above

ambient.

42

Page 61: LosAlamos - International Atomic Energy Agency

o Powered Electrode

40

20

0

00

/’ o

0

:~ Temperature after power shutdown

I Intefior Chamber Wal}

[-

a /.—-— -—.

7 IM—Chamber Ambient Air

o 50 100 150

Plasma Processing Time (rein)

Figure 23. Temperature Rise in Plasma Reactor.

3.11. Uncertainty in Measurements

Accuracy and precision of the measurements were estimated. Accuracy

was assessed from iiquid scintillation measurements of 15 samples of uranyl

nitrate with varying volumes between 25 and 100 microliters each converted to

U02 by the method previously described but without plasma processing. These

samples were obtained over the course of the experiments. The intent was to

verify that the initial activity could be recovered. The results are depicted in

Figure 24 indicating that on average, 97% of the original uranyl nitrate activity .

was recovered by the liquid scintillation process described earlier.

The precision, or uncertainty in determining the fraction of UOZ etched,

~R, was ~ 2.0 % (Figure 25) which included uncertainties due to: counting

statistics; isotope activity ratio; activity of the initial solution; pipette volume; mass

measurement; ratio of aiiquot to total sample solution; counter efficiency;

planchette area; and aipha/beta

uncertainties were large occurred

misidentification. The cases for which the

when the plasma immersion time was less

43

Page 62: LosAlamos - International Atomic Energy Agency

than 30 minutes, or the absorbed power was less than 40 W, or when pressure

was too low (- 10.8 Pa) or too high (- 40 Pa). The “following paragraphs

describe how these estimates were made. I

The uncertainty or standard deviation, cfG, or the reiatiW? error, eG, of a

function G are functions of the individual measurements, xi

uncertainties, 0=,, or relative errors, ei. They are calculated

(Bevington, 1969):

)G= G(x1,x2,... ,

~: =~(;:c=j)2 f1

6GeG =?.

Applying equation (19) to the functions, NR A, etc. resulted

functions tabulated in Table 11. Al! radioactive source standards

and their

as follows

(18)

(19)

(20)

in the error

and known

constants (molecular weight, counting time, half-life, Avogadro’s Number) were

assumed to be error free.

The uncertainty in the observable are tabulated

uncertainty in the counter efficiency was determined for

in Table 10. The

the least accurate

counter used, the surface alpha scintillation counter, which provided a worke

case error for LSC counting. A known 239Pusource was counted and the reiative

counter el%ciency error was determined by the relationship shown in Tabie 11.

Manufacturer’s specifications used the largest error reported for the range of

these experiments. These included uncertainties for a graduated cylinder,

Eppendorf pipette, and Mettlar balance. The uncertainty in plasma processing

time varied with power. Below 250 W, the power was applied or removed

immediately and an uncertainty of - 10 seconds was taken as an average error.

Above 250 W, application of power was siowiy ramped to the desired value

which vaned from -2 minutes below 500 W, and -5 minutes above 500 W.

These ramp times were taken as the uncertainties. The isotopic ratio error

44

Page 63: LosAlamos - International Atomic Energy Agency

applied Poisson counting statistics using the relationship noted in Table 11. The

value shown was based on the alpha energy spectrum used to determine the

isotopic ratios. The uncertainty in the diameter of the stainless-steel planchette

was based on the measured standard deviation from all 12 planchettes. The

probabilities of an alpha emission being counted in the alpha window, and the

probability of a beta emission being counted in the beta window were based on

the 2% incorrect identification of alpha and beta emissions (Figure 17).

The counter uncertainty was calculated for each datum applying Poisson

(Bevington, 1969) counting statistics, Equation (21). In this approach, the

uncertainty, ax, in the total counts, Z, in the appropriate alpha or beta window is

related to the counting time, t, and the measured instrument count rate, C. or CP.

Since the counting time was determined by the liquid scintillation counter’s

internal clock, its error was negligible in comparison to the counting emor. Thus,

IfOz= x, (21)

Table 10. Measurement Uncertainties

(22)

Symbol Description

Counter efficiency~V Graduated cylinder volume accuracyf Isotopic ratio

Mettler Balance AccuracyYP Pipette volume accuracy (Eppendo~dP Planchette diameter~ Piasma immersion time (depends on

power)O~p S 250W

250c P< 500W500< Ps1200W

pa= probability an alpha counted in alphawindow

pPp probability beta counted in beta window

2,, Specific activity of uranyl nitrate solution

Relative Absolute UnitsError, e Error, o for a0.015 -

0.2 ml0.032 -

0.2 mg0.016 -

0.016 cm

10 s

2 min5 min

0.98 0.01

0.98 0.010.015 –

45

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1.05

1.00

0.95

0.90

1

.-—

Recovery: 97%

I

-J-—.

L Activity recovered, A, of original uranyl nitratesoltiion, AO,following conversion to U02,

dissolving in HNO~, and LSC Counting.

5 10

Test Sample Number

Figure 24. Accuracy of the Measurements.

15

50 I

40

30

20

10

Relative Error Distribution in NR

Most Probably Error 0.02

i

Figure 25.

0.2 0.4 0.6 0.8 1.0

Relative Error, e~R

Uncertainty in Measured Fraction of UOZ Etched.

46

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3.12. G!ow Discharge Observations

For typical etch operations, the NF3 gas flow was started and the pressure

allowed to stabilize before RF power was applied. Power application resulted in

an increase in pressure and sheath voltage, as shown in Figure 26. The

pressure increase was due to the dissociation of the NF3 and a net increase in

moles of gas created. After about 7 minutes, both pressure and sheath voltage

had stabilized, and therefore the zero reference for the plasma immersion time

was set at seven minutes for all experiments. At the end of the desired plasma

immersion time, RF power was removed which caused a drop in pressure to

below initial conditions. When power is removed, dissociation stops while the

gas flow continues. Recombination reactions, both in the chamber volume and

on surfaces, result in a net decrease in moles of gas, leading to pressure below

the initial pressure. After 4 to 5 minutes, pressure had increased to the initial

pressure, reflecting a return to the initial conditions.

25 ~

I RF On Sheath Voltage RF Off;\~e. ------- ----- ____1 i

20

NF~ On

at- 20 minq5 . –.—

III1

I

‘E!!!H—.—-—.—-—- —- —.-— ,~_–

I ---4 ~ Time to stabilize ;VI I

hlF~Off

at -66 min—-—

120

60

40

0o 50

Plasma Process Time (Min)

Figure 26. Typical Plasma Operations.

The glow discharge in the chamber during processing had a magenta

tinge. The glow was brightest near the antenna at all pressures, filled the entire

chamber in the vicinity of 17 Pa, and was brightest in the range 17 to 35 Pa. At

47

Page 66: LosAlamos - International Atomic Energy Agency

higher pressure and low power, the glow region shrunk towards the antenna and

was surrounded by a dark region extending from the grounded walls of the

chamber to the glow discharge edge. As power increased, the glow region

expanded outward from the antenna, eventually filling the entire chamber as

power increased further. Figure 27 and Table 12 shows the glow discharge

region as a function of pressure at 50 W. The radius of the glow discharge

volume, R, ranges from O at the center of the RF antenna to the maximum

radius, R~a, at the test chamber wall. At 7.5 Pa, the glow region radius, R, is -

11 cm, and the volume increases as pressure increases. At 16.4 Pa, the glow

discharge fills the entire volume and this continues to above 17 Pa. At -23 Pa,

the glow region starts to shrink again, becoming -18 cm in radius at 25.7 pa and

continuing to shrink until at 41.3 Pa, the glow is veiy small and the brightness

has decreased significantly. The glow is brightest at 16.4 through 35.2 Pa, and

decreases in brightness at either extreme of pressure. The sheath around the

cathode RF antenna remained bright at all pressures except the lowest (7.5 Pa)

and the highest pressure (41.3 Pa) and the visual thickness of the sheath also

varied with pressure.

I R=-llan

1

(a) 7.5 Pa (c) 16.4Pa 1

(d) 25.7 Pa (e) 35.2 Pa (f) 41.3 Pa

Figure 27. Glow Discharge Observations at 50 W Absorbed.

48

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Table 11. Equations and Related Error Functions.

Name Relationship Error

Activity Ratio RemovedlvR N~=l-~

“b

Alpha or Beta Countc,+ O~J=(7 =

Rate, Cj, i = ~ or ~.2’) J_Xj

Count Rate, C c = Ca -t-(l-paa)ca –(l–ppfl)cfl ~c =(Count correction appliesonly for liquid UCscintillation)

ec. —c

Activity, A(tP) ~ d&(fp)= eA=[edY+(e,Y+(ec)’ +kf,)+(e,}]’2

7Initial Activity of sample, ~ Z/LAll = ) +(d’ +(’, Y]”o

L’

Plasma Process Time, tP t~ 0.1667e =—, for O< PS250 Watts

IF tp

e = ~ , for 250< P S 500 Watts‘P P

e = ~ , for 500< P S 1200 Watts1P P

49

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Table 11. Equations and Related Error Functions.

Name Relationship Error

Dilution Factor, d v“

Jr

2

(Based on volumetric d = ~a“,

e~ = i- e~P~method),

Dilution Factor, d (mg - mO)1/2

(Based on gravimetric(m,. –mO)2 +(mg - mgo)2 +(mg –mo)*

‘=(mg-mg~) (7” = Crmmethod) (mg - row)’

o~ed=—

dDilution Factor, d d=l cr~=e~=O(Based on counting entire

sample)

Counter 13fficiency, q x–B ~ d-(Used error for surface q = Af =

v Atalpha counter which gavea relative error much ~=m

larger than LSC)v x-B

Isotopic Ratio, f f = Counts of ~in spectra over

r

fcounts of all others in spectra % = ( f)– l-i-

x

Jl+fef =

fx

Area of Planchettes, S nd2 dd = diameter s=~ (SS=-j-ad

50

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Table 12. Plasma Observations

Pressure Sheath Sheath Bulk Plasma Plasma Plasma Plasma Color(Pa) Voltage Brightness* Radius (cm) Brightness* Brightness*

(v) (Center) ?4R7.5 -266 8 11 5 3 purple13,3 -235 10 22 6 5 purple/magenta16.4 -173 10 25 7 7 magenta25.7 -127 10 18 8 5 intense

magenta35.2 -55 10 10 8 5 intense

magenta41,3 -5 7 5 4 2 weak magenta

*Subjective brightness scale, range O (dark) to 10 (brightest).

51

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CHAPTER 4. RESULTS

The experimental results presented in this section are taken from over

250 plasma etching experiments (Appendix C). First, the etching process is

described in terms of an example that describes the parameters used for

analysis. Next, the experimental data on the effects of power and pressure on

the initial and average etch rates are presented and discussed.

4.1. The Etching Process

The measured activity of the uranium dioxide removed from the substrate

surface normalized to the initial activity of the sample, NR, is plotted in Figure 28

versus plasma immersion time. The data closely follows an exponential function

of the form

iv, = ivR,m (l-e-q (23)

In the above equation, NR,ma is the asymptotic fraction of UOZ etched at

the end-point, t is the plasma immersion time, and r is the characteristic etch

time. The end-point, as defined in this work, is when all detectable U02 in the

sample has been etched or the etch rate becomes almost zero, with UOZ in the

sample only partially removed. The plasma immersion time was corrected by

seven minutes to account for the time

pressure and sheath voltage. In the

determined from least squares fit to

respectively.

needed for the plasma to reach steady

figure, the values of NR,_ and ~, as

the data, are 0.96 and 52.7 minutes,

The U02 etch rate, J(t), can be expressed, based on equation (23), as:

()dN NRm :=Je:J(t)=&= - e o“

T(24)

In the above equation, the term (NR,~~/~ ), or Jo, is the initial etch rate at t

= O, (0.0182 rein-l), and is shown in Figure 28 as the slope to the curve for NR

versus t at t = O. Conversion of the etch rate in rein-l to thickness or mass of the

sample etched per unit time is described in Appendix E. The etch rate J(t)

52

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approaches almost zero after -4 characteristic etch times and occurs at 210

minutes in this example. ~ The self-limiting nature of the etch process is

demonstrated in the above two equations by the term (1-e-z). This term

represents the blocking effect of the U02 surface during” processing to further

reaction with the atomic F generated in the bulk plasma to form a volatile UF6.

The blocking term varies from unity at t = Oto zero at the end-point.

_ ‘R.max J!_-—+--* —-Un d

-./JT = 52.7

< —.II

NR = fll~s(l - e-)

I

b

Initial Etch Rate, JO= 0.0182 rein-l (0.5 ~m/min)

#

.% .’I ❑17 Pa

50 wt

‘o 100 200 300

Plasma Process Time, t (Min)

Figure 28. Fraction of UOz Etched in NF3 RF Plasma.

4.2. Effect of Absorbed Power

Figure 29 shows the U02 etch data taken at 17 Pa, while the absorbed

power was varied from 25 to 210 W. The corresponding values of /V~,~~ and ~

are summarized in Table 13, al~ng with the initial etch rates, Jo. Except for 25 W,

all the UOZ in the samples was etched to the underlying substrate given enough

time in the plasma. The characteristic etch time varied from 52.7 minutes at 50

W to 8.9 minutes at 210 W. Three samples (not shown) were processed in

53

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The trend of the results at 10.8 Pa was similar (Figure 32), except that at

both 25 and 50 W, NR,~= did not approach 1.0, a complete removal of the UOZ

before blocking occurred. This shows that even though the sheath voltage

increased from -140 V at 17 Pa to -176 V at 10.8 Pa (Chapter 3), the higher

energy resulting from ions accelerating through the higher sheath potential was

not enough to maintain the etch reactions. The fraction etched decreased as

pressure decreased from 17 Pa to 10.8 Pa, implying that the F atom

concentration decreased. As power increased above 100 W, however, NR,m=

reached 0.96 with ~ decreasing to -30 minutes.

plasma for 24 hours at 50 W, and there was no detectable UOZ left in any of the

samples. Over 99% of the initial U02 was removed at 210 W afier 37 minutes.

At 25 W, fU~,ma did not reach one (i.e., full removal), indicating that complete

removal of detectable U02 could not be achieved at the end-point. The initial

etch rate, Jo, in the present experiments varied from 0.22 to 3.11 microns per

minute, depending on the values of the gas pressure and the absorbed power in

the plasma. These data show that increasing the absorbed power increased

hl~,~a and decreased t, thus increasing Jo, the initial etch rate.

After four characteristic etch times, either ail UOZ was removed or the etch

rate reached zero. This is demonstrated in Figure 30 and Figure 31 which

depicts the length of time needed to achieve the value of h&/,mx shown in Table

d3. NR,~a approaches 1.0 above 50 W, but is significantly reduced below 50 W.

The figures also show that there is little incentive to process beyond four

characteristic times, with little improvement realized at five characteristic

processing times.

The highest fractions etched were realized at 32.7 Pa (Figure 33) with

NR,mx approaching one (complete Uoz removal) and z approaching less than 10

minutes. At 25 W, etch results were similar to the lower pressure results, with

‘ Detectableas definedin Chapter3 forthe criticaldetedlon level.54

Page 73: LosAlamos - International Atomic Energy Agency

blocking occurring before U02 could be completely removed. At 180 W, over

999’o of the U02 was removed in just 17 minutes.

,

At 39.4 Pa (Figure 34), NR,~a at 50 W was less than unity. These results

are similar to the case at 10.8 Pa, suggesting that the combination of pressure

and power needs to be optimized to achieve the

pressure is either too high or too low for the

decreases.

1.0

2K

Oa 0“83‘5c 0.60.=oCOk 0.4w2~u 0.2

o’

Table 13. U02 Plasma Processing

highest etched fractions. If the

power used, the etch fraction

Results at 17 Pa.

Absorbed NR<.m r Initial Etch Rate JoPower (W) (rein) (rein-’) (pmlmin)

25 0.54 68.0 0.0079 0.2250 0.96 52.7 0.0182 0.50100 0.98 28.0 0.0350 0.97168 0.97 12.3 0.0789 2.18210 1.00 8.9 0.1124 3.11

-.—-~-—-—.—-—-—-—--t+ -—-—-—-—-n a

[i?/ ‘210 ~ u w

168 AAl 00~o 50

f?

‘v’ v vv v

v

@!J

100 200 300

Plasma Process Time, t (Min)

Figure 29. Power Effects on U02 Etching at 17 Pa.

55

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21OW

0.5 Lo 100 200 300 400

Plasma Processing Time, t, to Achieve /VR~~X(rein)

Figure 30. Effect of Power on NR,m.. at 17 Pa

60

45

30

15

“o 100 200

Plasma Process Time, t, to Achieve

300

N~,~=(min)

400

Figure 31. Effect of Power on ~ at 17 Pa

56

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2“

1.0

0.8

0.6

0.4

0.2

0

.—-— -—-— .— -—-— -—-— - —-— .I

o

]10.8 Pal

o 100 200 300

Plasma Process Time, t (Min)

Figure 32. Power Effects on U02 Etching at 10.8 Pa

1.0

0.8

0.6

0.4

0.2

n

-—-— -—-— -—-— .— -—-—- —-

132.7 Pal

-.0 100 200 300

Plasma Process Time, t (Min)

Figure 33. Power Effects on UOz Etching at 32.7 Pa

57

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1.0

0.8

0.6

0.4

0.2

0

[

P=50W

o 30 60 90 120

Plasma Process Time, t (Min)

Figure 34. Power Effects on U02 Etching at 39.4 Pa

4.3. Effect of Plasma Gas Pressure

The pressure effects at 25 W of A/~ versus plasma processing time are

shown in Figure 35. At this power setting, the complete removal of U02 was not

achieved at any pressure. But 17 Pa yielded the highest etch fraction, ~R,~~ =

0.54. At both 10.8 and 31 Pa, the amount etched decreased compared to 17

Pa.

At 50 W and 17 Pa, NR,~~Xapproached 1, indicating the complete removal

of U02 (Figure 36). But at both 10.8 and 39.4 Pa, complete removal of U02 was

not achieved, with similar results at both pressures.

At 100 W, complete remova} of U02 was achieved at all pressures

between 10.8 and 39.4 Pa (Figure 37) with characteristic etch times ranging from

70 to 14.1 minutes as pressure increased. At 170 W (Figure 38), similar results

were achieved but with significantly faster characteristic etch times ranging from

30.5 to 3.7 minutes.

58

Page 77: LosAlamos - International Atomic Energy Agency

To summarize the pressure variation data, increasing the NF3 gas

pressure increased the amount etched, /V~, up to a peak pressure, then the

amount etched decreased as summarized in Figure 39. Above 50 W, ~R

increased monotonically with pressure in the pressure range examined. In

principle, the F atom concentration should decrease with increasing pressure at

constant power because fewer NF3 molecules will dissociate and some F atoms

will recombine to F2 in the plasma and on the chamber walls (Hinz et. al., 1980).

However, in our plasma reactor, the brightening of the glow near the antenna

and the shrinking glow region implied that the effective plasma volume

decreased while ionization increased closer to the antenna. Hence, as pressure

increased, the actual F atom density increased. This effect continued up to a

maximum pressure, then the F atom density decreased, as suggested by the

decreasing amount etched as pressure increased further. In the region where

etching increased monotonically with pressure, the highest etch fractions were

achieved. For example, at 32.7 Pa and 100 W, 99% of the UOZ was removed in

just 17 minutes, compared to 37 minutes at 17 Pa and 210 W.

.— - —-—. — -—- —.— -—-—- —-— -—-—-—-

b .

0 100 200 300

Plasma Process Time, t (Min)

Figure 35. Pressure Effects on U02 Etching at 25 W.

59

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1.00

0.75

0.50

0.25

1--- —- —- —-.–- +- —-*–- —-- —-o-1

wQ

o

n

—10.8

u50 w

-.0

1.00

0.75

0.50

0.25

0

100 200

Plasma Process Time, t (Min)

Figure 36. Pressure Effects on U02 Etching at 50 W.

300

a .— -—-—-—- —-—-

R.4

I.w!!!l

50 100 150 200 250

Plasma Process Time, t (Min)

Figure 37. Pressure Effects on U02 Etching at 100 W.

60

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1.00

0.75

0.50

0.25

.-

170 WI

o 30 60 90 120

Plasma Process Time, t (Min)

Figure 38. Pressure Effects on UOZ Etching at 170 W

1.0

0.8

0.6

0.4

0.2

00

.- —-— -—.—- —-— -A

c1

t = 53 min

10 20 30

Pressure (Pa)

Figure 39. Pressure Effects on U02

61

40

Etching.

50

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4.4. U02 Etch Rates

Figure 40 shows the experimental initial etch rate, $, at 17 Pa and the

trends at other pressures. In developing this chart, some data which did not

include sufficient data points to establish t+~= with reasonable confidence were

not included, such as the high and low pressure data at 25 W. In addition, the

units used for equation (24) were converted to micrometers per minute by

multiplying by the factor 27.64 (Appendix E). These results may be converted to

milligrams per minute by multiplying equation (24) by the factor 13.56.

The baseline data at 17 Pa shows that the initial etch rate increased from

0.2 to 3.1 pm/min as absorbed power increased from 25 W to 210 W. Increasing

pressure generally increased the etch rate, to 7.4 ~m/min at 32.7 Pa and 180

W. When power was set too low for a given pressure, the etch rate also dropped

as indicated by the 39.4 Pa data points. Decreasing pressure (e.g., to 10.8 Pa)

generally resulted in a lower etch rate and this effect was related to the

decreasing brightness of the glow discharge near the antenna, and hence lower

F atom concentration in the bulk plasma.

The average etch rate, ~, needed to compare these results with the

reported PuG average etch rates (Martz et. al., 1991), was obtained by

integrating equation (24) as shown below:

(25)

The average etch rate at 17 Pa is plotted in Figure 41 as a function of

power for values oft/z = O, 2, and 4 where the latter value represents the etching

end point. The experimental etch data for th va~ing between 3.5 to 4.5 is also

plotted showing good agreement between prediction and experiment. the

62

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average etch rates at the end point ranged from 0.1 to 0.7 pmlmin between 50

and 200 W. The equivalent mass etch rate is also shown for comparison.

0.1

0.01L J

10

1

0.1

50 100 150 200

resorbedPcYw3r(w)

Figure 40. Initial Etch Rate of UOZ. ~

Experimental Data, 35s U, s 45

8

00, ~o 50 100

Power

Figure 43. Average Etch

150 200

Rate at 17 Pa.

10

1

D.1

1

0.1

0.01

63

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CHAPTER 5. CHEMKIN

To understand the physics of the etching process, it was necessary to

determine the type and concentrations of the reactive plasma species in an N~

plasma, including those that react with the UG to form gaseous UF6. Such a

determination was made using an existing RF piasma discharge code,

CHEMKIN Ill: A Fortran Chemical Kinetics Package For The Analysis Of Gas-

Phase Chemical And Plasma Kinetics. CHEMKIN had been previously applied

to silicon etching in CF~02 and NF~02 plasmas with good results (Meeks et. al.,

1997; Meeks and Shon, 1995). The following discussion describes the

CHEMKIN code, the code validation, and the code predictions for the present

experiments.

5.1. CHEMKIN Description

CHEMKINti, a chemical kinetics code developed by Sandia National

Laboratory, is a collection of modules for modeling chemically reacting flows in

chemical reactors and in RF glow discharge plasma. It consists of a number of

Fortran modules or subroutines, data files, script example problems, and

documents to facilitate the modeling of chemical kinetics. It models the chemical

kinetics of reactions in the gas phase and at a gas/solid interface to include the

transport and interactions of ions, molecules, and radicals. Three basic

modules used to model the present experiments were Cl-lEMKIN, SURFACE

CHEMKIN, and AURORA. The AURORA module was selected because it

modeled the plasma as a continuously stirred tank reactor (CSTR) which most

closely approached the experimental conditions of these experiments at 17 Pa.

A utility, FITDAT, was also available to generate thermodynamic polynomial

coefficients in the form needed by CHEMKIN and SURFACE CHEMKIN to carry

out the calculations.

i CHEMKIN is availabie from Reaction Design, 11436 Sorrento Valley Road: San Diego, California92121, Tel: (649) 550-1920

64

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The CHEMKIN module (Kee et. al., 1996) solves elementary gas-phase

chemical kinetics, including multi-fluid plasma systems that may not be in

thermal equilibrium. The SURFACE CI-IEMKIN module (Coltrin et. al., 1996)

solves problems involving elementary heterogeneous and gas-phase chemical

kinetics in the presence of a solid surface. SURFACE CHEMKIN was used in

conjunction with CHEMKIN to model the NFs plasma reactions in the present

experiments, but not to determine the etch rate. The AURORA module (Meeks

et. al., 1996) predicts the steady state or time averaged properties (density,

molecular weight, flow rates, etc.) of well-mixed plasma systems and predicts the

ion, electron, and neutral species concentrations in the bulk plasma. It applies

the continuously stirred tank reactor (CSTR) approximation. The module

characteristics are specified by a reactor volume, residence time or mass flow

rate, heat loss or gas temperature, surface area, surface temperature, incoming

gas temperature and mixture, and net power deposition into the plasma. The

module runs in conjunction with CHEMKIN and SURFACE CHEMKIN. Typical

output parameters from CI-IEMKIN are summarized inTable 14.

Table 14. Typical Output Parameters,

Parameter

Mass flow rateTemperature: gas, ions, electronsPressureMean densityMean molecular weightMean volumetric flow rateSCCMResidence timeMole fraction of each speciesConcentration of each speciesMolar flow rate of each speciesMass flow rate of each speciesVolumetric flow rate of each speciesSCCM of each speciesSurface site fractions (etching)Bulk site fractions (etchina)

65

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5.2. The CSTR Approximation

Cha@cterization of the plasma reactor and recovery system in terms of,

pressure and flow of gaseous products is determined from the mole balance

Consider a chamber whose volume, V,continuity equation (Fogler, ” 1992). ‘

contains gases whose total pressure is p, has an inlet flow of to moles of

species j per unit time, t, and an outlet flow of ~ moles per unit time. The

applied RF power causes some of the gas to dissociate while other processes

cause species to undergo other reactions, including recombination, for a net

molar production rate of species j, ~. The net production of moles of species j in

the chamber is the partial derivative of the number of moles of species j,qj. The

mole balance then becomes

F,O-F,+G,=Zd

(26)

The Aurora module for a plasma assumes steady state, so the

partial derivative becomes zero. Assuming no surface production of species

(i.e., no etching), the

formation of species

becomes:

F,. - F+jrjdv=o.

production rate, Gj, is the integral of

j per unit volume, f, and the mole

the molar rate of

balance equation

(27)

The CSTR approximation implies that within the volume, all the species

are perfectly mixed and the outlet conditions are identical to the conditions inside

V. Thus, the integrai becomes simply the product of f and V, and, after

rearranging, becomes:

Fjo -F,v= (28)

–r, “

Equation (28) is the design equation of the CSTR approximation (Fogler,

1992). Essentially, this approximation reduces all the differential equations to a

system of linear algebraic equations, greatly simplifyhg the solution of the

plasma chemistry. It will be shown below that this approximation results in the

66

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need to restrict the use of CHEMKIN to conditions at 17 Pa in the present

experiments.

5.3. Plasma Reactions in CHEMKIN

Mass spectroscopy investigation of NE plasma species were conducted

by a number of investigators (Perrin et. al., 1990; Reese and Dibeler, 1956;

Konuma and Bauser, 1993; Greenberg and Verdeyen, 1985; Honda and Brandt,

1984). h&F2 was identified by excimer laser photolysis of NE (Weiner et. al.,

1992) and ~ radicals by laser-induced fluorescence (Lui et. al., 1992). The...

cracking pat,temlt’ of NF3 by electron bombardment was measured by mass

spectroscopy (Beattie, 1975). The species identified are listed inTable 15. The

fact that not all species were identified by all the experimentaiists is only

indicative of the instrument and focus of the experimentalists’ work. CHEMK}N

includes all the species observed, except ~F+ which only Konuma and Bauser

(1993) observed and F2-which only Reese and Dibeler (1956) observed .

The plasma reaction set for CHEMKIN (Table 16) was obtained from

Sandia (Meeks, Private Communication, 1998) using their N~02 reaction set

(Meeks et. al., 1997). All reactions involving oxygen, and all but four typical

electron-neutral excitation reactions for N6, N2, N, and FZ were removed since

these reactions were not of interest for the bulk plasma and doing so improved

the computer processing time considerably. Reaction #35 was added for NF and

NF2 reactions with NF2 (Du and Setser, 1993). Based on the validation work

discussed below, the rate coefficients for reaction #17 was decreased by a factor

of 10 in order to increase NFs dissociation while reaction numbers f 2, 14, 15,

and 16 were increased by a factor of 10 and reaction #36 was added to bring the

N2 and N concentrations into agreement with the experimental work of Perrin et.

al. (1990).

‘“A cracking patternk definedas the fragmentsof a molecule that form when the parentmoleculeis exposed to an ionizationsource, but withoutthe presence of a plasma.

67

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%i

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Definitions and units used in Table 16 are summarized below

Units:

EXCI:

REV:

TDEP/E/:

Molecules, cm3, seconds, Kelvin.

Electron energy loss per collision (eV) due to excitationreactions.

Signifies that the reverse reaction rate values to followare to be used rather than equilibrium values.

Reaction depends on the temperature of the specieswithin the slash marks, in this case the electrontemperature (as opposed to the gas temperature).

The forward rate coefficient, kf is given by equation (29) and is the

defining equation for the constants given in the tabie. EA/R has units of K; EA is

the activation energy in kJ/mole; R is the gas constant (8.3144 J mol-l IC1); B,

the exponent of the temperature, is dimensionless; T is the temperature (K); and

~, the reaction rate constant, has units of (cwz’nzolecule~-]s-’, where n is the

order of the reaction, varying between O and 3. The reverse rate coefficient,

when it applies, is calculated from the REV keyword value or, when REV is not

given, from equilibrium kinetics (Appendix D).

(/)EA R-—

kf = koTBe T(29)

Table 16. Plasma Chemistry in CHEMKIN.

Reaction Type of Reaction b B EJR Keywords10NIZATION/DISSOCIATION/ATTACHMENTREACTIONS

1 E+ NF3~ NF3++2E 7.39E-34 5 38t11TDEPIEt

2 E+ NF.3+NF~++2E+F 2.25E40 6.46 34184TDEPIEI

3 E+NF3 ~NF+ +2E+2F 3.93E-6311.0439849TDEP/E/

4 E+NF2+ NF2++2E 2.21E-33 4.94 31902TDEP/E/

5 E+ NF+NF++2E 1.94E-42 6.8 33586TDEP/E/

6 E+ N2+N2++2E 2.56E-43 7.07 31481TDEP/E/

7 E+ N+ N++2E 5.11E-37 5.78 47602TDEP/E/

69

Page 88: LosAlamos - International Atomic Energy Agency

Tabie 16. Plasma Chemistry in CHEtvlKIN.

Reaction Type of Reaction b B EJR Keywords8 E+ F2j F~++2E

9 E+ F+ F++2E

10 E+NFs~NFZ+F+E

11 E+ NF3+NF+2F+E

12 E+ NF2+NF+F+E

13 E+ NF2+N+2F+E

f4 E+ NF~N+F+E

15 E+ N2F2+2N+2F+E

16 E+ NpF.+~2N+4F+E

17 E+NF3sNF2+F-

18 E+ F*+ F+ F-

RECOMBINATIONREACTIONS

t9 E+ N+~N

20 E+N2+~N+N

21 E+ N2++N2

BIMOLECULAR & 3RD BODYREACTIONS

22 N+ N+ Me Nz+M

23 NF2+M@NF+F+M

24 NFP+NFP+M~NzF4+M

25 i=+F+ M@ F2+M

26 NFz+FP@NF3+F

27 NF+NF@N2+F+F

28 NF+NFe F2+N2

29 NF+N2F2eNF2+N2+F

30 NF + NF2 ~ N2F2+F

31 NF2+N@F+F+N2

32 NF2+Ne NF+NF

33 NFz+F+M@NF3+M

34 F+ N3QNF+N2

35 NF+NF2e N~+3F

36 NFP+ NF2@ N2+4F

ION-IONMUTUALNEUTRALIZATIONREACTIONS

37 F-+ NF~+~ 2F+ NF2

38 F.+ NFZ+~ 2F+ NF

39 F-+NF+ aF+NF

40 F-+N2+ ● F+Nz

41 F-+N+ +F+N

42 F-+F2+ +F+F2

43 F-+F+ ~F+F

CHARGETRANSFERREACTIONS

1.64E4

2.24E-47

2.06E-17

1.35E-30

1.57E-16

1.69E-23

1.57E-16

2.28E-16

2.28E-16

1.49E-09

1.02E-05

2.25E-O?

2.25E-01

2.25E-01

1.41E-32

1.26E-09

1.50E-32

2.80E-34

3.00E-14

6.88E-11

4.00E-12

2.00E-12

3.75E-12

1.40E-11

3.00E-12

1.03E-30

5.80E-11

2.75E-15

1.50E-32

1.00E-08

1.00E-08

1.00E-08

1.00E-08

1.00E-08

1.00E-08

1.00E-08

7.25 32663TDEP/E/ ;

7.81 34076TDEP/E/

1.72 37274TDEP/W

4.45 34210TOEP/E/

1.& 27565TOEP/E/(ko=10-original)

2.99 37652TDEPIEI

1.84 27565TDEP/E/(IQ=10*01’i9inaI)

1.7 36391TDEP/E/(ko=10=original)

1.7 36391TDEP/E/(ko=10*onginal)

-0.14 3751TDEP/E/(ko=O.10*original)

-0.9 1082TDEP/E/

-2.5 0 TDEPIEi

-2.5 0 TDEP/E/

-2.5 0 TDEP/E/

o 0 REVI 3.163E-07-0.5113200.f

O 25700

0 0

0 0 REV17.600E-12O. 14300.I

o 4860

0 1251

0 0

0 0

0 187

0 95

0 0

0 0 REV13.98OE-10O. 16417.I

o 0

0 3095(Added,Du&Setser,1993)

o 0 (Added,k= k,m24)

o 0

0 0

0 0

0 0

0 0

0 0

0 0

70

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Table 16. Plasma Chemistry in CHEMKIN.

Reaction Type of Reaction b B EJR Keywords44 F++l=z~Fz++F 9.7OE-10

45 F++N ~N+ +F 1.04E-09

46 F+ + NF3~ NF3++F 1.16E-09

47 F++ NFa NF++F 1.23E-09

48 F+ + NF2~ NF2++ F 1.30E-09

49 F2++N ~N++F2 9.37E-10

50

51

52

53

54

55

56

57

58

59

60

61

F2++ NF3~ NF3++ F2

F2++ NF ~ NF++ F2

F2++ NF2~ NF2++ F2

N2++N aN+ +N2

Nz++ NF3● NF3++ N2

N2++ NF ~ NF++ N2

N# + NF2● NFz++ N2

N+ + NF3● NF3++ N

N++ NF~NF++N

N+ + NF2~ NFz++ N

NF++ NFZ~ NF2++ NF

F++ N2=N2++F

1.04E-09

l.ll E-09

1.17E-09

9.37E-10

1.04E-09

l.ll E-09

1.17E-09

9.7OE-10

1.03E-09

1.08E-09

9.I5E-10

9.7OE-10

o

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

“oo0

0

0

0

0

0

0

0

0

0

0

0

0

EXCITATIONREACTIONS(TYPICAL)

62 E+ NF3+E+NF3 3.42E-21

63 E+ N2+N2+E 2.02E-34

64 E+ N~N+E 1.25E-39

65 E+ F2+F2+E a 1.09E-51

2.52 33296E)(CU7.70/ TOEP/E/

5.29 36200EXC1/13.00/ TOEP/E/

6.07 38618EXC1/13.70/TDEP/E

8.54 37389EXC1/13.06/TOEP/E/

5.4. Surface Reactions

The surface reactions modeled are the wall fluorination, ion wall

recombination, and, for the validation case, the fluorine reactions with surface

silicon (Table 17). Etch reactions for U02 were not modeled since the objective

was to determine reactive species concentrations in the bulk plasma (and

therefore at the plasma/sheath interface) for input to another model (E1-Genk et.

al., 1999). The constant, y, is defined as a sticking coefficient when the keyword

“STICK” is used and as a correction to the BOHM velocity when the keyword

“BOHM” is used. The sticking coefficient is a dimensionless quantity defined as

the reaction rate divided

the reaction (Meeks et.

by the incoming flux of species, and is the probability of

al., 1996, p. 83; Coltrin et. al., 1996). The BOHM

71

Page 90: LosAlamos - International Atomic Energy Agency

correction is an approximate method of correcting for transport conditions to the

surfa~e, accounting for the ion density gradient which affects the transport of

ions near the walls (Meeks et. al., 1996, page 83). The keyword needed in the

CHEMKIN input file is included in Table 17.

Table 17. Plasma Surface Reactions.

Type Reactions YFluorination of Aluminum Walls (STICK KEYWORD)

F + AL(s) + /@) 1“

F + ALF(s) ~ ALF2(S) 1F + ALF2(s) ~ ALF3(s) 1F2 + AL(s) + ALF2(s) 1F2 + ALF(s) S ALF3(s) 1

Ionic Wall Recombination (BOHM KEYWORD)F++E~F 0.4F2++E+F2 0.4N++E~N 0.4N2++E+N2 0.4NF++E~ NF 0.4NF2+ + E ~ NF2 0.4NF3+ + E * NF3 0.4

Silicon Etch Reactions (For Validation with Perrinonly) (STICK KEYWORD)

F + Si(s) * SiF(s) 1F + SiF(s) S SiF2(s) .01F + SiF2(s) ● Sil%(s) 1F + SiF3(s) + Si(b) ~ SiF4 1

The fluorination reactions with the chamber walls have sticking

coefficients (STICK KEYWORD) of 1.0 because passivation of the aluminum

wall sutiace is fast, requiring less than 60 seconds in a fluorine bearing plasma

(Mayumi et. al., 1990) to form AIFs (Miller and McCluskey, 1991). The

intermediate fluorination reactions were developed based on the concept of

successive reactions of a diffusing F or Fz atom (Mauer et. al. 1978, Flamm &

Donnely 1981).

Ion recombination reactions will occur on the side walis of the chamber

with much greater occurrence than on the powered electrode, because the area

of the wall is much greater than that of the powered electrode. The resulting

72

Page 91: LosAlamos - International Atomic Energy Agency

highly asymmetric discharge means that the voltage drop through this sheath is

only on the order of a coupie of volts (L’ieberman and Lichtenberg, 1994, p. 370).

Because the implementation of AURORA provides only a single value for the ion

energy loss through a sheath, the grounded wall sheath potential (2 V) was

applied. in addition, the BOHM coefficient adjustment of 0.4 (Table 17) was

applied based on values suggested by Sandia (Meeks et. al., 1996, page 83).

For silicon fluoride reactions, the sticking coefficients (STICK KEYWORD)

for all but the reaction leading to SiFz were set to 1.0. There were two reasons

for this approach: (1) to maintain the successive fluorination step sequence

from Si to the volatile SiF4 (Mauer et. al. 1978, Flamm & Donnely 1981); and (2)

to modify only a single reaction as the rate limiting step. This seiection was

somewhat arbitrary because the objective was to generate the experimentally

observed SiFA and the intermediates were not necessary. Consequently, the

sticking coefficient was adjusted until a value of 0.01 resulted in the value

reported by Perrin et. al.(1 990).

5.5. Thermodynamic Constants

CHEMKIN contains a thermodynamic database with values of specific

heat at constant pressure, enthalpy, and entropy as a function of temperature.

The ionic species thermodynamic data not in the database were obtained from

Sandia (Meeks and Veilieux, 1998) and are listed in Appendix D.

5.6. CHEMKIN Validation

Only one source of NF3 plasma mass spectroscopy data was found that

provided the data needed to make a species quantity comparison with

predictions from CHEMKIN (Perrin et. al., 1990). In that experiment, the

concentrations of the neutral plasma species were determined by combining

mass spectroscopy data with relative ionization probabilities. In cases where

data was lacking (e.g., N2Fg), the authors were able to estimate the quantities

from the total system pressures and the partial pressures of the other gases.

They conducted their investigations at 50, 100, fl50, 200, and 300 W but only at

73

Page 92: LosAlamos - International Atomic Energy Agency

200 W did they provide total system pressure from which to estimate the partial

pressure of ‘othefl species. Their experiment consisted of a heated plasma

“box” inside a larger chamber. The plasma was created inside the “box” whose

‘heated interior side-walls contained the silicon. The plasma species and etch

products flowed out of the “box” toward the pump and the mass spectrometer,

resulting in recombination reactions within the outer chamber and walls during

the transport (Figure 42). As a result of this transport, ions and short-lived

species would be expected to recombine, and consequently Perrin et. al. (1990)

only measured NFs, Nz, SiFA, certain species which they attributed to N2F4, and

other gases, including HF. The HF came from a plasma-deposited film of SiHA

used to coat the interior of the plasma box prior to NF3 etching. The etch

process was monitored by laser reflectomet~.

Table 18 summarizes the plasma “box” parameters (Perrin et. al., 1990)

that were modeled in CHEMKIN. Dimensions of the outer chamber were not

available. Because of the recombination during transport to the mass

spectrometer, in comparing CHEMKIN, we assumed that only the long lived

species would retain their identify and that ions and short lived species would be

transformed into their parent species as summarized in Table 19. Consequently,

the mole fractions of the parent species are the sum of the mole fractions of the

individual plasma species listed. The contributions to the “Other” category

includes F and Fz. The authors did not observe Fz (or F) until after the silicon

etch end point was reached. At that point, the Fz mole fraction increased from -

0 to over 0.36, indicating that silicon was no longer consuming F atoms. In their

experiment, any excess F would react with H and other impurities. Therefore, all

F and F2 species predicted by CHEMKIN were included with “other parent

species.

74

Page 93: LosAlamos - International Atomic Energy Agency

Table 18. Parameters of Pernn et. al. (1990) Experiments.

Item Value

Volume (ma)

Area (m2)

Power (W)

Pressure, no plasma (Pa)

Pressure, plasma (Pa)

Flow (SCCM)

Wall Temperature (K)

Si Crystal Dimension (m)

Si Site Concentration (mole/m2)

Al Crystal Dimension (m)

Al Site Concentration (mole/m2)

0.0128

0.4480

200

10

12

140

575

5.43xlo-’0

5.63x10~

4.04xlo-’0

4.05XI 0-5

Table 19. CHEMKIN Species Consolidation.

Long Lived Plasma SpeciesParent SpeciesNF3 NF3N2 N, N2, N3, N+, N2+SiF4 SiFAOther NF2, NF, N2F2, N2F4, F2, F, F+, F2+, NF+, NF2+, NF3+, F-

The comparison of experimental results (Perrin et. al., 1990) with

CHEMKIN was best performed in terms of mole fractions, xj, of species j, and so

the conversion of measured concentration ratios was made from the relationship

shown in equation (23). Here, pj is the partial pressure of species j, p is the total

pressure with plasma (12 Pa), p. is the total pressure without plasma (1 O Pa),

and Cj/Co is the concentration ratio reported by Perrin et. al. (1990) in their figure

8. The results of this conversion are tabulated in Table 20.

P,

[1

CJ Pox,=—= — — (30)

P cop”

75

Page 94: LosAlamos - International Atomic Energy Agency

Table 20. Pernn et. al. (1990) Experimental Data at 200 W.

Species c$c~ 3NFs 0.253 0.211N2 0.315 0.262SiF4 0.408 0.340Other (HF, N2F4) 0,224 0.187TOTAL 1.200 1.000

Several iterations were performed starting with the original CHEMKIN

chemistry reaction set (Table 16), and adjustments were made to the reaction

rate constant value, ~, until the experimental mole fractions for all the species

were in agreement. Because there are many interactions in the chemistry which

could alter the results in unexpected ways, the changes to the rate coefficients,

k, were kept to within one standard deviation of the expected error of the original

reaction set k value. For example, in reaction #l 7, the electron attachment

reaction was reported to have a k-value (Miller et. al., 199S):

3477*695

k = (1’i 4)x10-12~ Tcm 3 (31)

s – molecule ‘

The values of k reported in the original CHEMKIN data set (Meeks et. al.,

1997), as well as 0.1 and 10 times the k values, were bounded at 298K within

the error bars of (EA/R), ~ 695 K, of the original rate coefficient for reaction 17, as

demonstrated in Figure 44. The rate coefficient reported by Miller et. al. (1995)

was a factor of 1000 less than the original (Meeks et. al., 1997), further

supporting a reduction of the rate coefficient. But because of the constraints on

the allowed modifications, the final value of k selected was 0.1 times the original.

The next change in the k-values was for the quantities of N, N2, and N2F4,

whose predicted mole fractions were too low with the original set (Meeks et. al.,

1997). Applying the same limitations as described above, values for the rate

constant, k. (see Equation (29)), for reactions #12, 14, 15, and 16 were each

increased by a factor of 10, and reactions 35 and 36 were added. The two latter

reactions were added because they had been reported in the literature (Du &

Setser, 1993).

76

Page 95: LosAlamos - International Atomic Energy Agency

The final result was an overall error in the mole fractions of the reported

neutral species NF3, N2, SiF4, and all others of less than A 5.3%, as shown in

Figure 43. The worst case relative error for any of the parent species was t 5.3

%. A detailed listing of CHEMKIN predicted mole fractions of the NFs plasma

species is included in Appendix D. These results suggest that the CSTR

approximation inherent in the AURORA module of CHEMKIN is suited to the

experimental conditions of the Perrin et. al. (1990) experiment. However, even

here there were anomalies. Perrin et. al. (1990) reported that the etch rate

increased with pressure between 12 and 15 Pa, then decreased between 15

and 35 Pa. These results, whose trend was confirmed with the present

experimental data, demonstrate that AURORA can only be applied to cases

where the CSTR approximation can be applied.

Estimates of the species partial pressures were made (Appendix D), but

without knowing the partial pressures of the “other” species, accurate

comparisons with CHEMKIN were not possible except at 200 W.

hJF3Gas inlet

t

HeatedWalls .

Cold ~Walls

I MassSpectrometer

I

Plasma4

Box

I I

Iu kTypical GasDiffusion Pathto Mass spec.

- pump

Figure 42. Experimental Setup of Perrin et. al.

77

Page 96: LosAlamos - International Atomic Energy Agency

co.-2

Ii

0.5

0.4

0.3

0.2

0.1

0

Figure

I o-”

10-’3

10-’5

10-’7

10-’9

piq ,5;K a’NF. Plasm hamber Conditions

200 W, 12 Pa, 140 SCCM

NF31

N2

43. Comparison of CHEMKIN with Si Etching Experiments.

~E3Reaction #17:

e+ NF3+. NF2+F-

2.5 3.0

k+= 1.49x1 0-8T a“14e-(3751*g5w

k.= 1.49x104 T 4“14e-3751m(Meeks et. al., 1997)

k-= 1.49x10-%0”14e-(3751- ‘g5)n

/Miller et. al., 1995

3.5 4.0 4.5 5.0

1Ooorr

Figure 44. Maximum Variation in Rate Coet%cient.

78

Page 97: LosAlamos - International Atomic Energy Agency

5.7. CHEMKIN Predictions for the Present Experiments

With the set of final plasma chemistry reactions defined above,

predictions of the mole fractions of the various species of the NFs plasma for the

conditions of the U02 experiments were evaluated, but under conditions of no

etching. Consequently, the surface reactions (Table 17) were implemented with

only the ionic and wali fluorination reactions. The objective was to obtain the

reactive species concentrations at the plasma sheath interFace for use in another

simulation (E1-Genk et. al., 1999). Because of the CSTR approximation inherent

in the CHEMKIN modeling, the CHEMKIN mole fraction predictions for these

experiments are given only for 17 Pa (see paragraph 5.8) with Appendix D

containing detailed mole fraction data.

The CHEMKIN input parameters describing the U02 experimental plasma

conditions are tabulated in Table 21. Most of the parameters are self-

explanatory. Power was allowed to vary from 25 to 250W absorbed. The

volumetric flow rate, in SCCM, was set in CHEMKIN to the flow rate determined

from manufacturer’s calibration correlation needed to achieve 17 Pa at the power

specified. The heat transfer coefficient, 1486 W m-2 S-l, produced a neutral gas

temperature that remained nearly constant over the range of power (Table 22).

Table 21. CHEMKIN Parameters for the UOZ Experiment.

Item Value

Volume (m~) 0.125

Area (m2) 1.604Power (W) 25 to 250Pressure, plasma (Pa) 17

Flow (SCCM) 5.34 to 5.7

Ambient Temperature 298(K)H [W m-2 S-l} 1486

The predicted effect of power on the major neutral species mole fractions

are shown in Figure 45. Neutral species not shown had mole fractions less than

0.001. As power increased, predicted NF3 dissociation and F atom mole fraction

79

Page 98: LosAlamos - International Atomic Energy Agency

Table 22. CHEMKIN Parameters at 17 Pa.

Power (W) SCCM Neutral Gas Electron(cm3/min) Temperature (K) Temperature (eV)

25 5.71 298.1 5.615075100125150

175200225250

5.675.635.595.555.515.465.425.385.34

298.2298.3298.3298.4298.5298.6298.6298.7298.8

5.215.014.874.774.684.604.534.464.38

both increased. The increasing F atom concentration with power is in agreement

with the experimentally observed increasing etch rate with power. The predicted

ion mole fractions are shown in Figure 46, with the negative F ions having the

highest predicted mole fraction, approaching 1.8 x 10-5 at 200 W. ionic species

not shown had mole fractions less than 10+. The NFs inlet flow rate, in SCCM;

the electron temperature, in eV; and the neutral gas temperature, in K, are

tabulated in Table 22. The inlet flow rate variations reflect the experimental

pressure variation with power previously discussed. Predicted mole fractions of

all species are tabulated in Appendix D.

The predicted effect of pressure, at constant power, is demonstrated in

Figure 47 for F and NFs species, indicating that the F atom concentration is

predicted to decrease with increasing pressure as the NF3 concentration

increases. Since F atoms are the primary etchant species (see Chapter 6), this

would indicate that the etch rate shotild decrease with increasing pressure, a

conclusion that is not observed for all experimental conditions. For example,

below -50 W, the etch rate increased with pressure until a peak pressure -23

Pa was reached, then decreased. CHEMKIN predicts the decrease, but not the

increasing and peak pressure. Above - 50 W, the experimental etch rate

increased throughout the pressure range 10.8 to 40 Pa, never reaching a peak.

These results indicate that the CSTR approximation cannot be applied under all

80

Page 99: LosAlamos - International Atomic Energy Agency

conditions. Above 17 Pa, the plasma glow region, hence the effective plasma

volume, decreased, an aspect that is not modeled ~th the CSTR approximation.

‘ Below t 7 Pa, the glow volume region also decreased, again suggesting that the

CSTR assumptions are not met. Only at 17 Pa was the glow visually uniform,

suggesting that 17 Pa is the only pressure region in which CHEMKIN can be

applied.

Several variations were investigated to understand the sensitivity of

various parameters, including fiow variations between manufacturer’s and

experimental flow measurements, and variation in heat transfer coefficients. The

inlet flow rate variation of NF3, in SCCM, differed slightly between manufacturer’s

flow correlation and experimentally measured values. These differences were

inconsequential at all pressures, as demonstrated (Figure 48) for NFs neutrals

and ions at 10.8 Pa, for which pressure the greatest variations occurred. Several

variations in heat transfer coefficient were also investigated. Under adiabatic

conditions, CHEMKIN predicted that the plasma temperature would increase to

well above 1000 K, a situation which did not occur experimentally. Finally, a heat

transfer coefficient equal to 7.53 W m-2 S-l yielded a wall temperature equal to

the experimentally measured temperature at 50 W and 17 Pa (Chapter 3). This

condition resulted in a neutral gas temperature varying from 300 to 311 K in the

power range 25 to 250 W, which appears reasonable. Between 1486 and 7.53

W m-2 S-l, mole fractions of NF3 varied from 0.796 to 0.799 while F mole fractions

varied from 0.150 to 0.153, respectively. However, because of insufficient

temperature data throughout the pressure and power range, operation at near

constant gas temperature obtained at the higher heat transfer coefficient was

used.

CHEMKIN predicted that NF3 and F-atoms are the predominant species in

the NFs bulk plasma. The F atom mole fraction increased with power as the NFs

mole fraction decreased. However, the predicted pressure variation at constant

power did not follow the experimental variation in etch rate because the CSTR

approximation did not apply throughout the pressure range.

81

Page 100: LosAlamos - International Atomic Energy Agency

4L

F

c 0.1 :0.=umLal62 0.01 :

EEl

0.001 I 1 I !

o“ 50 100 150 200 250

Power (W)

Figure 45. CHEMKIN Neutral Species Predictions at 17.0 Pa.

I t i 44

w

104 ( I I I

o 100

Power (W)

Figure 46. CHEMKIN Ion Predictions

82

200

at 17.0 Pa.

Page 101: LosAlamos - International Atomic Energy Agency

0.02

O.ofl

0.005

0.002

0.001

0.0005

10°

10-2

104

10 20 30 40

Pressure (Pa)

Figure 47. CHEMKIN Pressure Predictions.

NF3

‘- ~-- 5-- $-- G--

1O*t I

o 50 100 150 200 250

Power (W)

Figure 48. CHEMKIN Sensitivity with Flow Rate

83

Page 102: LosAlamos - International Atomic Energy Agency

5.8. Limitations on the Use of CHEMKIN

The CSTR approximation applies to the plasma

experiments only to a degree, and this was only

conditions of these U021

determined after many

comparisons of the CHEMKIN predictions with the present etching results. The

problem was that the concentration of species in the test chamber for U02

etching was not uniform at all pressure and power levels used, as noted in the

experimental chamber observations in Chapter 3. The glow, which is

representative of a convolution of species density, electron distribution, and

cross section for electron impact (Lieberman and Lichtenberg, 1994, p.254), was

brightest near the antenna at all pressures, filled the entire chamber at 17 Pa,

and was brighter at 17 Pa than at 10.8 Pa in the power range used. At higher or

lower pressures, the glow region shrunk towards the antenna, and was

surrounded by a dark region extending from the grounded walls of the chamber

to the edge of the glow discharge. As power increased, the volume of the glow

discharge region expanded outward from the antenna, eventually filling the entire

volume at high enough power.

completely uniform throughout

ranges used in the experiments.

These observations imply that mixing was not

the test chamber for all pressure and power

The CSTR approximation appears valid only near 17 Pa at all powers where the

glow fills the chamber but has intensity variations. CHEMKIN provides the

correct trends of the effect of changing power, but not of pressure, primarily

because the effective plasma volume is not constant, as required by the CSTR

approximation. CHEMKIN predicted that the F atoms are a major constituent of

the plasma, which is confirmed experimentally (Perrin et.al., 1990; Pelletier,

1987; and Flamm et. al., 1981); that F atoms increase with powe~ and that F

atoms decrease with pressure. The power variation is correct, but the pressure

variation is not. To conclude, CHEMKIN provides useful data in species

predictions and quantities, but must be used with care when extrapolating the

results. In these experiments, CHEMKIN provided useful data at 17 Pa, but not

at other pressures because the CSTR approximation did not hold.

84

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CHAPTER 6.

The self-limiting

U02 ETCHING ANDPLUTONIUM

nature of U02 etching

APPLICATION TO

was demonstrated by the

experimental results of chapter 4. The nature of this self-limiting process is

reviewed in this chapter and likely causes identified. First, the plasma species

are examined to determine the etchant species. Next, thermodynamic

assessment of reaction products identify likely candidates that form non-volatile

products that block or slow the etchant reactions with U02 to form a volatile UFe.

These results are extended to plutonium based on similarities in the chemistry

and thermodynamics.

6.1. The Plasma Species

The plasma species and mole fractions predicted by the CHEMKIN code

(Chapter 5) are summarized in Table 23. The most abundant species are NFs

and F atoms, but F is the reactive radical which reacts with U02 to produce the

volatile UFG. Fluoride volatile products were also produced in silicon etching

experiments with fluorine bearing gases (Pelletier, 1987; Flamm et. al. 1981).

NF3 is non-reactive at the experimental temperature (- 300 K) and the other

plasma species are too low in concentration to be a significant factor. The F

atom concentration increases with power as also demonstrated by the increasing

experimental etch rate of U02 with power. The F atoms created in the plasma

diffuse to the U02 surface where they react with U02 to produce UF6. The

accumulation of UFG molecules in the sheath slow the flux of F atoms to the

surface, reducing the effective F atom diffusion coefficient by as much as 1570

(E1-Genk et. al., 1999), further blocking or slowing the reaction of U02 to UF6 with

plasma immersion time.

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Table 23. Calculated Mole Fractions of Plasma Species at 17 Pa.

Species 50 w 100W

NF3 I 0.80 0.61F 0.15 0.31N2 0.03 0.06F2 0.01 0.02NF2 0.01 0.01

NzF4 2.1 E-04 8.3E-05N 3.3E-07 8.2E-07N2F2 1.6E-09 7.OE-10

NF 2.3E-12 3.OE-12N3 5.2E-57 7.1 E-57Electrons 1.7E-09 6.7E-09

F- 6.6E-06 1.1 E-05ions 6.6E-06 1.1 E-05

The ions, while too few in number to contribute significantly to the etching

process, deposit energy on the sutface, enhancing the reaction processes by

removing non-volatile products from the UOZ surface. For example, the sample

substrate temperature in the UOZ etching experiments rose -40 K above ambient

compared to only 4 K at the walls of the chamber. The relatively high

temperature rise of the sample resuited mostly from ion bombardment.

Exothermic reactions of UOZ and F atoms deposit at most 62 J of heat in 30

minutes of plasma processing at 50 W RF compared to 680 J from ion

bombardment (Appendix E). Hence, most of the temperature increase will be

from ion bombardment. The ions, in traversing the sheath, will suffer collisions

since their mean free path is a factor of -5 to 10 smaller than the sheath

thickness (Appendix E). Consequently, the energy deposited will be less than

the sheath voltage, but still high enough to break bonds and heat the surface

(Table 24). The sheath voltage was obtained from experimental measurements

(Chapter 3), the electron energy and neutral gas temperature were obtained from

CHENIKIN predictions (Chapter 5), and the ion energy was calculated as shown

in Appendix E.

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Blocking of the etch reactions can arise during the reaction steps leading

to the formation of UF6Ythus requiring an understanding of the etch mechanism.

Table 24. Plasma Conditions at 17 Pa.

Parameter 50 w IoowSheath Voltage (V) -142 -261Electron Energy (eV) 5.21 4.87Neutral Temperature (K) 298.2 298.3Sheath Thickness (cm) 0.14 0.16NFs Ion Energy (eV) ?1.3 17.9

NF3 Ion Energy (kJ/mol) 1087 1731

6.2. Reaction Model

Since F atom radicals are the predominant reactive species in the plasma,

reactions of adsorbed F and U02 are the initiating events leading to the

formation of a uranium fluoride gas. Because U forms in the III-VI oxidation

states (Jacob et. al., 1980), compounds UF3 through UF6 and the oxyfiuorides of

uranium are the ones likely to form. The reaction mechanism to produce UFtj is

quite complex and therefore a model for the reaction of adsorbed F atoms with

UOZ was developed to simplify the chemistry. This model combines aspects of

electronic valence orbitals of uranium, probability theory, and thermodynamic

Gibbs free energy heats of formation and reaction as described below.

Before UF6 appears from the starting material, UOZ several intermediate

compounds of the fluorides and oxyfluorides of uranium will form. The highly

reactive F atom radicals will diffuse to the surface and adsorb to U02 surface

sites via physisorped van der Waals forces and chemisorption (Lieberman and

Lichtenberg, 1985). Reactions will occur with UOZ molecular sites to form

products of U-O-F, where U-O-F indicates several possible compounds involving

all three atoms. Taking the possibie combinations of U, O, and F atoms to fill the

electronic valence structure of the U atom (Alberty and Silbey, 1997, Table 10-3)

leads to several species including the oxyfiuorides and fluorides shown in Table

25. Several restrictions were applied to the reactions including: reactions can

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only proceed in a direction to increase the complexity of the molecule (i.e., no

dissociation reactions); only one U atom per molecule (i.e., U308 not

considered); no reactions with desorbed oxygen were considered; and bonding

with F occurs first with the outermost U valence orbital before the inner orbital.

The electronic structure shown in Table 25 for U depicts the bonds in order of

decreasing binding energy where, for example, the 6d1 electron will bind before

the 7s2 electrons.

Table 25. Bonding Sites for Reaction with F Radicals.

U O F Species Electronic MaximumStructure Bonding Sites

100U [Rn]5fJ7sz6d1 1101UF [Rn]5f~7s2 2102UF2 [Rn]5~7s1 1103UF3 [Rn]5~ 2I04UF4 [Rn]5? 2105UF5 [Rn]5f7 1I06UF6 [Rn] oIlouo [Rn]5f37s1 1lIIUOF [Rn]5f3 21 1 2 UOF2 [Rn]5~ 21 1 3 UOF3 [Rn]5f1 11 1 4 UOF4 [Rn] 2120U02 [Rn]5? 21 2 1 U02F [Rn]5f3 21 2 2 UOZFZ [Rn] 2

Next, the concept of probability of reactions of one or more F atoms with a

molecule was applied. Binary reaction probability suggests that the likelihood of

one F atom reacting with a U-O-F molecule is greater than two F atoms reacting

tith a similar molecule at the same time, and these probabilities are much more

likely than three F atoms reacting with another similar molecule at the same time.

This means, for example, that the probability of U02 reacting to form U02F is

greater than the probability of U02 retaining its identity until two F atoms interact

to suddenly produce U02F2. Thus, it is more likely that the sequence will be

UOZ to U02F to U02F2. Based on this assumption, reactions with up to two F

atoms reacting at a time were examined. The actual number of F atoms that can

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bind was also limited by the number of electrons in the outetiost electronic

orbital. Forexample, tithe 6d'otii@l isavailable, then only one bonding site will

be created. The results of this calculation are depicted in Table 25 as maximum

bonding sites. For UF3, UOF, and U02F, the maximum number of bonding sites

were limited to two atoms although the 5f-orbitai indicates three electrons are

available (5f3). In the case of compounds with fully saturated bonds (i.e., all

vaience band eiectrons of U are bound), such as UOF4 and U02F2, reaction is

assumed to be the abstraction of oxygen and thus the maximum number of

nearest neighbor F atoms is assumed to be two. UF6 undergoes no further

reaction and so the number of bonding sites is zero. Consequently, the number

of F atoms reacting were iimited to the maximum number of bonding sites, and

these resuits were used in assessing a sutiace etch reaction mechanism.

6.3. Thermodynamic Analysis of SurFace Etch Reactions

in Figure 49, the Gibbs free energy of formation is piotted for each of the

uranium species iisted in Tabie 25. This figure provides an indication of which

species are iikeiy to form from the starling material, U02, shown with a horizontal

iine. Species above the iine require energy whiie those beiow the iine can

spontaneousiy react. For exampie, from UOZ approximately 1000 kJ/moie is

needed to form U and reiease the 02. The piasma environment containing

energetic ions bombarding the surface (Tabie 24) and exothermic surface

reactions provide more than enough energy to form any of these products. As a

result, U02 may dissociate into U and 02. Consequently, reactions of F with both

U02 and U as the starting materiai were anaiyzed to determine the surface

species, based on favorabie Gibbs energy of reaction, GR, and restricting

reacting F atom radicais to the number of bonding sites. Standard state

conditions (298 K, 1 Bar) were appiied since the majority neutrai piasma gas

species are near room temperature and pressure corrections are negligible,

<0.075 kJ/moie (Appendix E).

A thermodynamic anaiysis of aii combinations of U-O-F reactions was

performed based on the maximum number of bonding sites shown in Tabie 25

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(Appendix E). A value of the Gibbs free energy of reaction, GR that is negative

is indicative of a reaction that can proceed spontaneously in the direction

indicated by the chemical reaction equation until equilibrium renditions for

products and reactants are met. Table 26 contains a listing of all favorable

(negative G~) thermodynamic reactions evaluated while Table 27 contains a

listing of all unfavorable (positive GR) thermodynamic reactions evaluated. The

table also includes the reaction enthalpy, which is positive for endothermic

reactions and negative for exothermic reactions.

Table 26. Favorable Thermodynamic Reactions of U-O-F.

No. Reaction HR* GR* .kJ mol-l kJ mol-’

2F + UF ~ UF3 -1618.8 -1485.61

234567891011121314151617181920212223242526

2F + UOF -3 UOF3F + UC)F + UOF2

F + UF2 + UF32F+UOF~UF3+02F+U+UF22F + UF3 ~ UF52F + U02 + UOZFZF+ LJF-+ UF2

F+ UO~UOF2F + UOF2 ● UOF4

F + UF3 + UF4F + U02 ~ UOZF2F + U02F2 + UF4 +022F + UF4 ~ UF62F + UOF2 ~ UF4 + OF + UOF3 ~ UOF4F + UOF2 ● UOF3F + U02F ~ UOZFZ

F + UF4 + UF52F + U02F2 ● UOF4 + OF + UF5 + UFtj(s)2F + U02F ~ UF3 + OzF+lJ+lJF2F + UOF4 ~ UFG+ O2F + UOZF ● UOF3 + O

-1124.8-1040.4-1050.4-867.6-689.8-731.8-727.3-568.4-644.4-578.4-487.4-292.9-415.3-396.2-314.6-494.0-84.4

-434.4-244.0-180.7-201.4-362.3-121.4-182.0-121.1

-1223.0-979.5-870.1-809.1-749.8-660.6-650.1-615.5-599.1-519.0-449.3-427.1-387.3-368.4-278.9-275.4-243.5-223.0-211.0-164.0-161.9-161.0-134.3-133.1-111.6-35.427 F + UOF3 ~ UF4 +-0 -230.2

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The surface products obtained from thermodynamically favorable

reactions (e.g., negative G~) starting with U02 is shown in Figure 50. Reactions

involving a single F atom are shown as solid lines while reactions requiring two F

atoms are shown as dashed lines, where the former indicates a greater

probability of occurrence. Two products, U02F2 and U02F, have GR values of -

650 and 427 kJ/mole, respectively, but because UOZF requires a single F atom,

it has a higher likelihood of forming. From UOZF, the likely path is to U02F2.

From there, two F atoms are required to continue the reaction, but the path to

UF4 is more likely than to UOF4 because of the former path’s larger negative

value of GR. From UF4, the most probable sequence is to UF5 then UF6. Other

reactants requiring two F atoms to proceed are possible, resulting, for example,

in UF3 and UOF3, but the reaction products obtained from single F atom

reactions are favored. By exception, the species that were not

thermodynamically favored (i.e., had positive GR values in reactions of F with U

or U02) included UO, UOF, and UOFZ. Consequently, the likely reaction

products formed from F radicals and UOZ are the uranium fluorides, UFM, and

the uranium oxyfiuorides: UOZF, UOZF2, UOFS, and UOF4.

Table 27. Unfavorable Thermodynamic Reactions of U-O-F.

No. Reaction m“ GR”kJ mot-’ kJ mol-’

1 F+ UOF4+UF5+0 19.4 28.82 F+ UOF+UI=2+0 182.8 61.03 F + U02F2 ~ UF3 + 02 72.0 62.04 F+lJO~lJF+O 106.8 77.55 F + U02F ~ UOFZ + O -36.7 132.06 F+UOFZ~UFS+O 172.8 170.47 F+lJO~F+lJ +0 228.0 212.08 F+ UOF4+UF4+F+0 263,8 240.19 F + U02F2 ~ UOF3 + O 313.0 248.010 2F + U02 ~ UF2 + 02 395.2 282.011 F+ U02F2 +UOF2+O+F 398.0 355.012 F+ U02+UOF+0 710.8 684.413 F + U02F ~ UFZ + Oz 688.1 709.114 F+U02 ~UF +02 963.6 897.515 F+ UOF2+UF2+O+F 1223.2 1040.5

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The reaction mechanism starting with U is shown in Figure 51. There is a

single path from U to UF but because the GR values of succeeding reactions are

significantly more negative, thermodynamics implies that UF will not remain on

the surface, but react to form UFZ then sequentially to UF3, UF4, UF5, and UF6.

The reaction from UF to UF2 or UF3 is probably vety fast, since no stable

uranium compounds in the first oxidation state are known (Bierrnan et. al., 1983).

Other paths requiring two F atoms are possible as indicated by the dashed line,

but less probable than the first reaction sequence. The reaction path from U to

UF6 is essentially a single path compared to the U02 mechanism with several

parallel paths.

0

-500g

F3 -1000x

&-1500

-2000

Uoe —. %

u Y‘F \ UOF T=298K

\ @ ‘Fz UOZF\, /p–

-?I

u I\ UF~ 3 U02F,

UOFZ‘-%UOF UOFg

3 &—UF4 % UF~

UF~ ‘-e

-2500 ~ I200 240 280 320 360

Molecular Weight (g/mole)

Figure 49. Gibbs Free Energy of Formation for Uranium Fluorides/Oxyfiuorides.

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I Surface ReactionsRea~onGMMFreeEnergy,G R(Wmok)at288K

IJ(<=2 i

--’-% UOF4-------:33-- ----uF6III -211

~% ~ uo F2- -s~’- - u ~ -162

Ii

~ UF5 b UF6\

-223 \-373

XF + lj~\

449.----.----ElJF6

427 I / 45 *,*

t~

U02F--’~ UF&- ----- ---- ---->UF6\ --\ ~ ~61

X-112 -A\

‘h -275UOF3 ~

Sotid Lines: requires 1 F atomDashed lines: requires 2 F atoms

UF5 “62 * UF6

UOF4 = - + UF6

Figure 50. Gibbs Reaction Energy, GR, for U02 Etching.

Surface Reactions

)C<=2

ReactionGibbsFreeEnergy,GR(IcJmoie)at 298K

xF+U-661

r ---- ---- - T

1“-134

UFIit

Figure 51.

.I ‘\

-1486 J \ -617---- ---- - ---- ---- - *

Solid Lines: requires 1 F atomDashed lines: requires 2 F atoms

Gibbs Reaction Energy, GR for U Etching.

UF6

UF6

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6.4. Volatile Surface Species

The volatility of the sutiace species will indicate which will ciesorb into the

gas phase and which will likely remain on the surface, blocking the reaction.

Figure 52 shows a, plot of the vapor pressure of the available data while Table 28

extrapolates the vapor pressure to 298K, and includes melting point data. While

the vapor pressure is defined as an equilibrium process of like compounds in the

gas and condensed phase, the vapor pressure provides an indication of whether

the material will remain in the condensed phase on the surface, or whether it will

vaporize. The vapor pressure correlations used are fisted in Appendix E. Since

the experimental operating pressure varies from 10.8 to 40 Pa at --298 K, the

vapor pressure must be compared at these conditions. The 24 kPa vapor

pressure of UFG (Lange and Forker, 1967) at 298 K (Figure 52) is well above the

operating pressures in the experiments, and therefore UFEiwill desorb into the

piasma. The vapor pressures of the known uranium fluorides (UF5, UF4, and

UFS) at 298 K are severai orders of magnitude iower than the piasma operating

pressures and these species wili remain in the condensed phase (Katz et. ai,

‘1986(a); Jacob et. ai. 1980). UF and UF2 vapor pressure data is unavailable.

However, the bond dissociation of these two compounds are on the

bond dissociation energy of UFA and much greater than the bond

energy of UF5 (Hiidenbrand and Lau, 1992), suggesting that

pressures are aiso much iess than the chamber operating pressure.

ai, 1986) and U02 (Ohse, 1979) both have high meiting points and

order of the

dissociation

their vapor

U (Katz et.

measurable

vapor pressures oniy above 1480 K

sutiace at the operating pressures

oxyfiuoride U02F2 has a measurable

and so both wiii remain as soiids on the

and temperatures of the piasma. The

vapor pressure oniy above 900 K and the

UOF4 vapor pressure is iower by a factor of neariy 10 (Lau et. ai., 1985);

consequently, both wiii also remain as soiids on the surface. Vapor pressure

data on the remaining oxyfiuorides, UOZF and UOFS, were not avaiiabie;

however, extrapolating the trends in the oxyfiuoride species (Tabie 28) suggests

that U02F and UOF3 vapor pressures shouid be between UOF4 and U02F2. If

this is the case, then U02F and UOF3 wiii aiso remain in the condensed phase at

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298 K. From this analysis, it is concluded that UF6 is the only species with a

vapor pressure above the plasma operating pressure at - 300 K, and will

therefore desorb into the gas phase.

106‘UFG(a) UF~(C)

Operating - U02(

102Region

UOzF2(e)

10-2

~;f/ ~

/—UOF4(e)

U (b) References

104 uF~(b)a. Lange& Forker,1967b. Katz et. al., 1986 Vol. L

UF4(C)c. Jacobet. al., 1980d. Ohse et. al., 1979e. l-au et. al., 1985

10-’0300 1000 2000 3000

Temperature (K)

Figure 52. Vapor Pressure of UFX Compounds.

Therefore, it is argued that the non-volatile products likely to form over the

U02 surface are the uranium fluorides, UF2.5, and the uranium oxyfiuorides:

U02F, U02F2, UOF3, and UOF4. UF may form, but will immediately be converted

to UF2 or higher fluoride. These non-volatile products account for the blocking

effect previously discussed. If power is too low or pressure too high, conditions

at the surface may be such that these compounds slow and eventually stop the

reaction of F and U02. The blocking effect may be minimized by operating with a

pressure/power combination that optimizes the F atom concentration and the ion

energy to increase the removal of non-volatile deposits. This is supported by the

present experimental results (Chapter 4).

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Table 28. Surface Species Volatility Data.

Species Vapor Pressure Melting Referenceat 300K Point

(Pa) (K)uFfj 24000 337 Lange and Forker, 1967 (p. 1450)UF5 2.7x1 0-11 673 Katz et. al. 1986 (Vol. 1,p.308)UF4 5X1020 1233 Jacob et. al. 1980 (p. 27)UF3 <<1 1273 Jacob et. al. 1980 (p 6)UF2 * * See discussionUF * * See discussionu <<1 1406 Katz e. al. 1986 (Vol. 1,p. 228),

UO* <<1 3148 Ohse et. al. 1979U02F ● * See discussionU02F2 <<1 Lau et. al. 1985UOF3 <<1 * See discussionUOF4 << I Lau et. al. 1985

6.5.

were

Applications to PU02

The average etch rates of U02 determined from the present experiments

compared with the reported etch rate of PU02 in a CFd02 RF plasma

(Martz et. al., 1991) operated at 50 W and 26.7 Pa, as shown in Figure 53 (see

Chapter 4 for definitions). Unlike the detailed U02 etch data, the PU02

measurements are only available at a single power and pressure, thus

significantly limiting the ability to compare the results. A t.h = 4 value for U02

provides a reasonable comparison to the PuO* etch rate since NR will have

nearly reached the asymptotic value, NR,~~X. At 50 W absorbed power, the

average etch rate at the end-point was 0.108 pm/min for UO* and 0.030 pm/min

for PU02, a factor of 3.6 times slower for PU02.

Experimental differences may account for some or all the differences

between the U02 and the reported PuOZ etch rates: pressure (17 vs. 26.7 Pa),

etching gas (NF3 vs. CF~02), and uncertainties in the gravimetric method the

authors used. Pressure differences can lead to significant etch rate differences

as found in U02 etching, and similar results are expected for PU02. The gas

used could be a significant factor because NF3 dissociates 10 to 25 times faster

than CF402, increasing the available F atom radicals responsible for etching

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(Ianno et. al., 1981). The reported gravirnetric technique for measuring mass

loss was prone to considerable error (Martz et. al., 1991) which would be

improved if the quantification methods developed here were applied. These

factors taken together suggest that the etch rate differences may be due more to

experimental conditions than to the differences in chemistry.

10

1

0.1

0.01

1 0 ExperimentalData. 35s ths45 th=o

U0217 Pa for U02

826.7 Pa for PuOZ

● PU02

Io 50 100 150 200

Power

Figure 53. Average Etch Rate ~ of U02 Compared with PUOZ

The vapor pressure of PuFG at 298 K is 14 kPa (Weinstock et. al., 1959),

comparable to 24 kPa for UF6 (Figure 54). Consequently, at the pressures of the

experiment, the PuF6 will desorb from the surface. The intermediate compounds

PUFIA are all solids at room temperature (Katz et. al., 1986 (a)), comparable to

the tJF2.5 intermediates, and will remain on the surface in the solid phase.

Although there is some evidence that PuF5 exists, it had not been isolated and

thermodynamic data was not available for this compound.

The thermodynamics of the PU02 and Pu fluorides (Figure 55) are similar

to that of the U02 system (Figure 49), suggesting surface chemistry similar to

that of U02. The major difference with the U kinetics is the reaction from PuF4 to

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PuF6, where an equilibrium condition exists as suggested by the neariy equal ~

values for the two compounds. The equilibrium rate constant, ~, as calculated

from the favorab)e Gibbs reaction energy of -95.6 kJ/mole (Aiberty and Silbey,

1997) for reacting PuF4 with two absorbed F atoms high}y favors the reaction to

PuFEi as indicated by the large ~

reactions of PU02 with adsorbed

PuFEi in an RF plasma system.

Kp = e-% =5.7X1016 .

value in Equation (32). Consequently, etching

plasma F atoms are also expected to go to

(32)

The above results suggest that PUOZ etching rates should be comparable

to that of UOZ, with similar constraints on etching due to the self-limiting etching

process and the formation of non-volatile compounds. The differences in

reported etch rates between PUOZ and UOZ etching may be due entirely to

experimental differences. Furthermore, increasing power and pressure will most

likely increase PUOZ etching, much like U02 etching increases with power and

pressure.

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106

105

104

1)

2)Lange & Forker, p. 1450, 1967.Weinstock et. al., 1959.

103250 270 290 310 330

Temperature (K)

Figure 54. Vapor Pressure of PuF6 and UFGCompared.

350

Pu Uo

T=298Ku UF

nPU02 \

•1U02

UOF2PuFA+ 2F e W6,

G~ = -95.6 kJ/mo! UF4UF5

‘G, Estimated PuF~ Not Observed-2500 ‘

200 240 280 320 360

Molecular Weight (g/mole)

Figure 55. Plutonium Compound Gibbs Free Energy of Formation.

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CHAPTER 7. SUMMARY AND CONCLUSIONS

A series of single effect, RF plasma, glow discharge experiments were

conducted using NF3 gas to decontaminate depleted uranium dioxide from

stainless-steel substrates. In the experiments, the plasma absorbed power was

varied from 25 to 210 W, the pressure from 10.8 to 40 Pa, and the NF3 flow rate

from 3 to 18.5 SCCM. Depleted U02 samples each containing 129.4 Bq were

prepared from 100 microliter solutions of uranyl nitrate hexahydrate solution.

Quantification of the remaining uranium foilowing plasma immersion was

performed with liquid scintillation counting with alpha/beta discrimination,

spectral counting was adjusted by gaussian and first order polynomial fits, and

the resulting measurement uncertainties were A 2~0.

Results demonstrated that U02 can be completely removed from

stainless-steel substrates after several minutes processing at under 100 W with

initial etch rates ranging from 0.2 to 7.4 pm/min. At 180 W and 32.7 Pa gas

pressure, over 99% of all U02 was removed in just 17 minutes. The data showed

that etching increased with power in the range of 10.8 to 40 Pa. A pressure

effect was also noted below 50 W in which the etching increased up to a

maximum pressure, -23 Pa, then decreased with further increases in pressure.

The etching process was self-limiting and decreased exponentially with

immersion time to the end point, which is defined as the point where either all

UOZ is removed or the etch rate becomes zero. At both low and high pressure,

and low power (< 50 W), the end point was reached before all U02 was

completely removed.

A computer simulation, CHEMKiN, was applied to predict the NF3 plasma

species in these experiments. The code was validated by comparison with

experimental mass spectroscopy measurements of NF3 plasma etching of

silicon. The code predictions were within t 570 of the measured species

concentrations. The code predictions of plasma species in the U02 experiments

were only applicable at 17Pa where the plasma volume filled the entire test

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chamber and

species.

F atom

intensity variations suggested adequate mixing of the plasma

raditils are the primary etchant species, diffusing from the bulk

plasma to the surface, adsorbing to the surface, and reacting with UOZ to form a

volatile UF6, which desorbs into the gas phase to be pumped away. Ions created

in the plasma were too low in concentration to have a major effect on etching.

However, because they are accelerated through the plasma sheath, they can

deliver considerable energy to break chemical bonds on the U02 surface and

thereby enhance the primary etching process.

A primary etch mechanism, based on thermodynamic arguments, was

identified in which F atom radicals react with U02 to form non-volatile products,

including uranium fluorides, UF2.5, and uranium o@uorides, U02F, U02F2,

UOF3, and UOFg over the U02 surface. Successive reactions with adsorbed F

atoms lead to UF6. The UF6 has a vapor pressure of 24 kPa, well above the

operating pressure at the gas temperature (-300 K) of the plasma, and, as a

consequence, desorbs into the gas phase. The other intermediate fluonides and

oxyfluorides are solids and remain on the surface, eventually slowing or blocking

the etch reaction as they accumulate. When power was too low, the reactions

completely stopped before all detectable U02 could be fully etched. The

accumulation of desorbing UF6 near the U02 surface reduces the diffusion

coefficient of F atom radicals in the sheath, further slowing the reaction

processes and hence the etch rate.

The PU02 experimental etch rate data were comparable to the U02 etch

rates measured in these experiments. The chemist~ and thermodynamics of

PU02 have many parallels

temperature (24 vs. 14 kPa)

many intermediate species.

with U02: similar vapor pressures at room

and favorable Gibbs free energy of formation of

Some of the uncertainties include incomplete

knowledge of the thermodynamics, no counterpart to UF5, and an apparent

equilibrium condition between PuF4 and PuF6 not observed in the uranium

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system. The U02 etch results indicate improving etch rates with power and

pressure, and a similar effect would be expected with PuOZ. The’ favorable

parallels suggest that further experimentation with PUOZ etching should be

continued to quantify the physics of the processes over the power and pressure

parameter space.

These results demonstrated that the RF plasma glow discharge is a viable

method for decontaminating UOZ from stainiess steel substrates. The results

further show that the RF plasma glow discharge has potential application to

transuranic waste, including Pu and PuOZ.

102

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CHAPTER 8. RECOMMENDATIONS FOR CONTINUED WORK

8.1. Experiments with Depleted U02

Early experiments with depleted UOP were conducted to determine the

ability of an NF3 RF plasma to etch radionuclides from the interior of aluminum

pipes. The preliminary results (Veilleux et. al., 1997) indicated that pipes with an

L/D (length to diameter) of 15.7 showed that contaminant removal exceeded

99.9Y0. However, these results were prelimina~, based on analysis at 50 W and

17 Pa only, and used quantification methods prone to considerable error, such

as surface alpha probes and gravimetric methods. Therefore, there is a need to

repeat these experiments with the quantification methods developed in the

present experiments using varying L/D pipes to quantify the effect of diameter on

the etch rate, as well as power and pressure effects.

The present experiments were conducted with an NFs plasma. While NFs

dissociates 10 to 25 times faster than CFd02 gas, NF3 is considerably more

expensive than CF~02. Therefore, there would be utility in comparing directly

the etch rates in different gases.

Experimental quantification of plasma and surface species would provide

information regarding all reactant species. Mass spectrometric sampling inside

the plasma coupied with actinometry would provide valuabie species

identification and quantity.

A smaii number of early experiments were conducted with high specific

activity 233U to determine monoiayer thickness effects on the decontamination

rate. It was found that the iast layer of U02 was extremeiy d’tilcuit to remove,

and is possibiy associated with the strong chemical bonds that can form between

uranium and the metaiiic eiements of stainiess steei, especially nickei. However,

not enough experiments were conducted provide a good statistical base.

Experiments with varying power and pressure are needed to better quantify the

preliminary resuits.

103

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8.2. Recovery system

Early experiments were conducted to determine the ability of the recovery

system cold trap to capture the UF6 removed from surfaces and to quantify the

results. These preliminary resuits suggested that at least 5070 of the initial U02

was captured, but the data base is small and the statistics poor. In addition, the

quantification methods used at the time were not good enough to obtain

statistically reliabie results. Capture of effluent gases in the recovery system and

species quantification by Fourier transformed infrared (FTIR) spectroscopy will

provide a method of performing a mass balance of etched species, and provide

a means of determining if UFG is deposited along recovery system components

or remains in the gas phase.

8.3. In-Situ Measurements

Measurements of temperature of the substrate as a function of power and

pressure would provide significantly improved kinetics data for the reactions to

better determine the activation energy of the reactions. In tumi this data would

be very useful in designing future etching systems and to assess scale-up of the

vacuum chamber and recovery system. In the current experiments, this was not

possible because the proper equipment was not available to assure safe

operation.

8.4. Pu & PUOZ work

The early experiments conducted with PUOZ and Pu metal were based on

essentially a single data point for power and pressure. A range of experiments

are needed to better quantify the etch rate over the parameter space of power

and pressure, much like was done with the U02 experiments. Fairly large

quantities of PU02 and Pu will be required since bulk metal etch rates are

needed, not just monolayer thickness. Therefore, these experiments will need to

be performed in a Nuclear Class II category facility.

104

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APPENDICES

~pendix A Properties ;●...............................0.......................*......................... 106

Appendix B. Experimental Details ................................................................. ‘1’t5

Appendix C. Data ............................................................................................ 138

Appendix D. CHEMKIN ............ ...................=................................................... 150

Appendix E. Analysis ..................................................................................... 158

105

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A’1.

were:

1958,

AZ.

APPENDIX A. PROPERTIES

Physical Properties

The physical properties are tabulated in Table A-1 and the data sources

Alberty & Silbey 1997, Katz et. al. 1986, Shackelford et. al. 1994, Pearson

and Lide 1993.

Thermodynamic Properties

The thermodynamic properties of select elements and compounds are

tabulated in Table A-2. The values are at standard state (1 bar, 298.15K).

References are to: Aiberty and Silbey, 1997; Antony et. al., 1995; Cacace et.

al., 1995; Hildenbrand and Lau, 1991; Hinz et. al., 1980; Katz et. al., 1986 (b);

Lide, 1993; Mallard, 1997; Venugopal et. al., 1992; and; Wagman et. al.,

1982.

A.3. Enthalpy and Gibbs Energy Of Reaction

The Enthalpy, H, and Gibbs, G, reaction energy are determined by

summing the respective formation energies of products and reactants according

to Equation (A-1) or (A-2). Here, v, is the stoichiometric coefficient of the species

j and is positive for products and negative for reactants. Hj is the enthalpy of

formation for species j, Gj is the Gibbs energy of formation for species j.

Elements have a zero Gibbs energy of formation at all temperatures. Because

the corrections for temperature and pressure are small in the range of the

experiments (Appendix E), Gibbs energies of formation at standard state are

given.

G, =~v,G, (A-1 )

HR = ~V,H1 (A-2)J

The reaction enthaipy and Gibbs energy in kJ/mole are summarized in

Table A-3 for reactions with possible uranium compounds that can form from

U02. In general, reactions with up to three adsorbed F atoms were aliowed and

106

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where more are shown, such a reaction is a summary reaction incorporating

several intermediate steps. A negative enthalpy indicates an exotherrnic

reaction while a positive value indicates an endothermic reaction. A negative

Gibbs reaction energy indicates that the reaction is thermodynamically possible

but doesn’t say anything about the rate of reaction. A positive Gibbs reaction

energy indicates that the reaction is not thermodynamically favorable. The

reaction could still occur, but energy at least equal to GR is required. The energy

may be available from previous reactions, if the reaction in question is a

successive reaction.

A4. Properties Of Stainless Steel

The composition of stainless steel is taken from Lide 1994, p. 12-27 and

tabulated in Tabie A-4.

lL5. Nuclear Properties

The nuclear properties of seiect isotopes are tabuiated in Tabie A-5. The

data is taken from Shieien 1992 and Waiker et. ai. 1989. A description of the

iattice types maybe found a text on Soiid State Physics (e.g, Dekker, 1963).

107

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Table A-1. Physical Properties Of Select Compounds

Item

AhAlAr

ECr-alpha

F

F2

FezNFezOsFe-alphaFeF2FeFsFeO

l===H20 (gas)HzO(liquid)HeHF (gas)NN2

N2F

N2F2

l====NFNF2NF3PU(s)-AlphaPuF3(S)PuF4(S)PuF6(g)

MW (g/mol)

28.t27.C39,$

52.C19.[38.(

125,7159,755.t93,(

112.671.s18.[18.(4.[

20.(14.(28.(47.(66.[

104.(20.:33.(52.(71.(

242,1296,’315.:353.(

Density MP (C) BP (C) LatticeType Latticea Latticeb Latticec 1St Atomic Electron Bond(g/cm3) (A) (A) (A) Ionization Radius(pm) Affinity(eV) Dissociation

Potential Energy(eV) (kJ/mol)

1.16E-03 3.392.70 660.4 2467.0 cubic 4.04 0.44

15.8 65.9cubic 2.88 0.67

1,69E-03 -219.6 -188.1 17,4 39.6 3.415.7 2.96 157.0

6.35 200.05.27 1565.0 hex-R 5,03

bcc 2.87 7.9 122,74.09 1000.03.52 1000.0 4.25.70 1369.0 1.49

5.14E-03 0.0 100.01.00 0.0 100.0

24.6 29.1-83.1 19.5

14.5 52.11.25E-03 -209.9 -195.6 15.6 949.6

12.811.9 87.921.6 35.412.0 261.911.6 145.6 1.7 275.0

2.96E-03 -206.6 -128.8 13,0 156.8 238.319.86 641.0 3232.0 monoclinic 6.18 4,62 10,96 176.49.32 1425.0 trigonal(LaF3) 7.09 7.257.05 1037.0 monoclinic(C2/c) 12.60 10,57 6.28

50.8 62.3 orthorhombic(Prima) 9.95 9.02 5.26●

108

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Table A-1. Physical Properties Of Select Compounds

Item MW (g/mol) Density MP(C) BP(C) LatticeType Latticea Latticeb Latticec 1S! Atomic Electron Bond(g/cm3) (A) (A) (A) Ionization Radius(pm) Affinity(eV) Dissociation

Potential Energy(eV) (kJ/mol)

PuF6(S) 353.0 4.86 50.8 62.3 orthorhombic(Prima) 9.95 9.02 5.26PU02(s) 276.0 11.46 fcc(Fm3m) 5.40Si 28.1 2.33 1410.0 2355.0cubic(Fd3m),diamond 5.43 5.43 5,43 1.39Ss (304) 54.9 7.90 1425.0 /-

U (gas) 238,0U (s-alpha) 238.0 19.05 1132.3 3616.0orihorhombic 2,85 5.86 4,95 4.0 177.5Uo860212 10.00 fctetragonal 5.36 5,55UZOS 8.35 orthorhombic 8.29 31.71 6.73UsFeOIO orthorhombic 6.51 7.53 16.14U308 842.1 8.41 trigonal 6.81 4,14U308(s) 642.1 8.39 1150.0 orthorhombic(C2mm) 6.72 11.96 4.15U6F13 17,70 tetragonalbc 10.31 5.24UF3(S) 295.0 8,95 1140.0 trigonal 7.18 7.35 1.5UF4(S) 314.0 673 960.0 monoclinic(C2/c) 12,60 10.79 8.37 1.7UFS(s-alpha) 333.0 5.81 400.0 tetragonal(14/m) 6.51 4,46 5.9 299.1UFS(s-beta) 333.0 6.47 tetragonal(142d) 11.46 5.20 5.9UF6(9) 352.0 1.90 64.0 56.2 14.4

UFg(S) 352.0 5.06 64.0 56,2 orthorhombic(Prima) 9.90 6.96 5.22 14.4UFez 13.21 fcc(Fm3m) 7.06Uo 14.10 BI (Fm3M) 4.93U02 (cr) 270.0 !0,96 2875.0 fcc(Fm3m) 5.47UOZ(NOS)Z*2HZ0 430.1U02(N03)2*6H20 502.1 2.81 60.2 116.0orthorhombic(cmc2) 13.06 6.02 11.45LJ0233 pseudocubic 5.41UOZFZ 346.0 6.37 rhombohedral(R3m) 5.76UOS(Beta) 7.15 orthorhombic 13.01 10,72 7.51U03 (s) 286,0 7.80 650.0 orthorhombic(Fddd) 9.81 19.93 9.71

109

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Table A-2 Thermodynamic Properties Of Select Species

species State H: Gf” s“ Cp” RefkJmoi_l kJmol-1 JK1morl J K1 morl

AIF 9 -258.2 -283.7 215.0 31.9 Lidep. 5-5

PJF2 ,9 -694.5 -704.4 264.2 45.9 JANAF,ref. 53

AIF3 c -1510.4 -1431.1 66.5 75.1 JANAF,ref.53

AIF3 9 -1209.3 -1192.7 276.7 62.2 JANAF,ref.53

F 9 79.4 62.3 158.8 22.7 Lide1993

F- ~9 -255.4 -242.6 I Wagmanet. al. 1982F+ 19 1766.4 1678.1 Wagmanet. al. 1982

F2 19 0.0 0.0 202.8 31.3 Lide1993

F2(ads) ads 6.6 Lide1993

Ffi 9 24.7 41.9 247.41 43.3 Wagmanet. al. 1982

F2& 9 18.0 17.1 I Wagmanet. al. 1982

Fe c 0.0 0.0 27.3 25.1lWagmanet. al. 1982

Fe203 c -824.2 -742.2 87.4 103.9

FeF2 c -711.3 -668.6 87.0 68.1 Wagmanet. al. 1982

FeO(Wustite) c -266.3 -245.1 57.5 48.1 Wagmanet. al. 1982

FO 9 109.0 105.0 216.8 30.5 Wagmanet. al. 1982

H@ 9 -241.8 -228.6 188.8 33.6 Lide1993

H20 I -285.8 -237.1 70.0 75.3 Ltie 1993

HF 9 -273.3 -275.4 173.8 Licie1993

N 9 472.7 455.5 153.3 20.8 Lide1993

N2 9 0.0 0.0 191.6 29.1 L* 1993

N2F 9 1214.2 1153.5 Cacaceet. al. 1995

IN2F2 66.0 Wagmanet. al.1982

N2F2 g (trans) 82.0 77.9 Wagmanet. al. 1982

N2F4 $1 -6.4 79.9 301.2 79.2Lide1993p.514

N3 9 413.0 345.8 225.5 40.7ChemkinPolynomialFfi

iNF 9 248.9 164.7 2?5.3 30.4 ?dlailafd1997,Lide1993

INF2 9 43.1 57.8 249.4 41.0 Lide1993

NF3 9 -132.1 -90.6 260.8 53.4 Lde 1993

NiUQ c -2556.0 -2616.5 202.9 Katzet. al. 1986

NiU3010 c -3942.0 4348.7 358.0 Katzet. al. 1986

,0 19 249.2 231.7 161.1 21.9 tide 1993

0- 9 101.6 96.5 Wagmanet. al. 1982

p+ 9 1568.8 1490.4 Wagmanet. al. 1982

!02 9 0.0 0.0 205.1 29.4 Alberty.and Silbey1997

103 9 142.7 163.2 238.9 39.2 Albetty.and Silbey1997

~Pu-a c 0.0 0.0 54.5 31.2 Katzet. al. 1986

\PuF 9 -116.0 -190.5 250.0 33.0 Katzet. al. 1986

1PuF2 9 -615.0 -703.6 297.0 51.0 Katzet.al.1987

PuF3 9 -1163.0 -1158.0 336.0 72.0 Katzet. al. 1987

lPuF3 c -1585.7 -1516.4 126.1 92.6 Katzet. al. 1986~PuF4 9 -1443.0 -1416.0 368.0 Katzet. al. 1987

110

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Table A-2 Thermodynamic Properties Of Select Species

species state H: G“ s“ h“ Refk.Jmor’ kJ mol-1 JK1morl J K1 morl

PuF4 c -1846.0 -1753.0 147.3 116.2Katzet.al. 1986t

PUF6 c -1662.0 -1728.0 222.0 167.0Katzet. al. 1988

PUF6 9 -1813.0 -1724.0 369.1 129.4 Katzet. al. 1986

PU02 c -1056.2 -998.0 66.1 66.3 Katzet. al. 1966

PuOF c -1139.0 -1082.1 92.0 Katzet.al. 1987

Ss (304) s 0.0 0.0 25.2 Katzet.al. 1966

u c,a 0.0 0.0 50.2 27.7 Katzet.al. 1986

u 9 536.0 491.0 199.7 23.7 Kak et.al. 1987

U2N3 C,p -736.0 -755.4 65 54.2Katzet.al.1966

UF 9 42.0 -72.0 252.0 37.9 Katzet. al. 1986

UF2 9 -53?.0 $25.2 316.0 56.0 Katzet. al. 1986

UF3 9 -1059.0 -1006.1 Katzet. al. 1986

UF3 c -1502.0 -1433.0 123.4 95.1 Katzet.al. 1986

UF4 9 -1599.0 -1519.1 Katzet. al. 1986

UF4 c -1910.0 -1820.0 151.7 116.0Katzet. ai. 1986

UF5 9 -1937.0 -1887.0 386.0 111.0 Katzet. al. 1986

UF5 c, a -2075.0 -1969.0 200.0 132.0 Katzet.al. 1986

UF6 9 -2147.4 -2063.8 377.8 129.6 Katzet. al. 1986

UF6(s) c -2197.0 -2068.6 227.8 166.8Katzet.al. 4986

UFS2 c -32.2 Katzet. al. 1986

UFe2 c -19.9 [Antonyet al 1995

UN c -290.8 -266 62.631 47.8 Katz;Venugopalet al 1992

UNQ c -37.91 Antonyetal1995

uNi5 c -39.5 Antonyet al 1995

Uo 9 21.0 20.0 Wagmanet.al. 1982

U02 c -1085.0 -1031.8 77.0 63.6 Katzet.al. 1986

U02F 19 -996.0 -1094.1 329.0 68.0 Katzet. al. 1986

U02F c -1298.5 -1396.6 329.0 68.0 Katzet.al. 1986

U02F2 c -1653.5 -1557.3 135.6 103.2Katzet. al. 1986

U02F2 9 -1351.0 -1246.9 -349.0 86.0 Katzet. al. 1986

U02F3 c Assumesameas U02F2

U03 c,a -1217.5 -1140.6 99.4 81.8 Katzet,al. 1986

UOF 9 -544.0 -516.8 Katzet. al. 1986

UOF2 c -1505.0 -1434.0 119.0 Katz et. al. 1986UOF2 9 -1117.0 -1217.2 336.0 79.0 Katz et. al. 1986

9 -1510.0 -1615.2 353.0 89.o Katz et. al, 1986c -1924.6 -1828.4 Katz et. al, 1986

‘ Valuenotgiveninref.,assumesvalueis0.95 timesenthalpy.- Valuenotgiveninref.,determinefromH andCp.- Valuenotgiveninref.,assumedequalto gas phasevalueminusdifferenceingastosolidvalueforU02F2.

111

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Table A-3. Enthalpy and Gibbs Energy of Reaction for F Atom Reactions withUranium Fluorides and @41uondes

Reaction HR GRkJ mol-’ kJ mol-1

F+ U+IJF2F + lJF + lJl=3

F+ UF--+ UF2F + UF2 + UF32F + UF3~ UF5F + UF3 + UF42F + UF4 ~ UF6F + UF4 -+ UF5F + UF5 -+ UFe(s)F+ U()~UF+OF+ IJO + F+lJ +0F+lJOalJOFF+ UOF+UF2+(32F + UOF ~ lJOF~F + UOF + U0F22F+lJOFalJF3+oF+ UOFZ~UF3+02F + UOF2 ~ UOF42F + UOF2 ● UF4 + OF + UOF2 ~ UOF3F+ UOF2+UF2+O+FF + UOF3 -3 UOF4F + UOF3 ●UF4 + OF + UOF4 ~UF5 + OF+ UOF4+UF4+F+02F + UOF4 ~UF6 + O2F + U02 + U02F22F + UOZ aUFZ + OzF+ U02+UOF+0F -I-U02 ~U02FF+ U02+UF+02F + U02F aUOFZ + OF + U02F ●UOZFZF + U02F +UFZ + 022F + U02F ~UF3 + Oz2F + U02F aUOF3 + OF + U02F2 -+ UF3 + 02F + U02F2 + UOF3 + O

F+ U02F2+UOF2+O+F2F + U02F2 + UF4 + 02

-121.4 -134.3-1618.8

-568.4-1050.4

-731.8-487.4-396.2-244.0-201.4106.8228.0

-644.4182.8

-1124.8-1040.4

-867.6172.8

-578.4-314.6

-84.41223.2-494.0-230.2

19.4263.8

-182.0-727.3395.2710.8

-292.9963.6-36.7

-434.4688.1

-362.3-121.1

72.0313.0398.0

-415.3

-1485.6-615.5-870.1-660.6-449.3-368.4-211.0-161.9

77.5212.0

-599.161.0

-1223.0-979.5-809.1170.4

-519.0-278.9-243.51040.5-275.4

-35.428.8

240.1-333.1-650.1282.0684.4

-427.1897.5132.0

-223.0709.1

-161.0-111.6

62.0248.0355.0

-387.3

112

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Table A-3. Enthalpy and Gibbs Energy of Reaction for F Atom Reactions with,, Uranium Fluorides and Oxyfiuorides

Reaction HR GRkJ mol-l kJ mol-1

2F + U02F2 ●UOF4 + O -180.7 -164.0

Table A-4 Composition Of Stainiess Steel

M Composition Composition Totai Per 1000(g/moi) (%) (304) 9

c 12.0 0.08!/0 0.0008 0.o’1 0.17Mn 54.9 2.00% 0.0200 1.10 19.95P 31.0 0.0570 0.0005 0.01 0.25s 32.1 0.30% 0.0003 0.01 0.17Si 28.1 1.00?40 0.0100 0.28 5.10Cr 52.0 18 to 20?40 0.2000 10.40 188.84Ni 58.7 8 to 12?40 0.1200 7.04 127.89Fe 55.8 Remainder 0.6485 36.21 657.61TOTAL 1 55.07 1000.00

143

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Table A-5 Nuclear Properties Of Select Isotopes

Isotope MW (g/mol) Half-L& Max Alpha Max Beta Max(yr) Energy Energy Electron (B:ig)

(MeV) (MeV) Energy(MeV)

‘3Ac 225.02 0.0274 2.15E+1814c

2tiCm‘lFr%d2wPa2’2P02’3P02’6P0*PU239PU

“Ra‘ORn‘kh‘%h

‘u‘u‘u‘u

14.00

244.06221.01147.92

234.04211.99212.99216.00238.05239.05224.02220.01

228.03234.04232.04233.04234.04238.05

573018.11

9.1 E-0675

2.2E-069.6E-091.3E-1 14.8E-09

87.7424065

0.009971.7E-06

1.9130.06603

721.59E+052.47E+054.47E+09

5.81

3.18

5.505.16

5.324.824.774.20

0.16 1.65E+14

2.99E+156.56E+211.19E+15

2.29 2.54E+226.48E+244.76E+27

1.29E+25

6.34E+142.30E+125.92E+183.45E+223.03E+16

0.19 0.0910 8.56E+170.1086 7.92E+140.0767 3.57E+110.1004 2.29E+110.0895 1.24E+07

114

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APPENDIX B. EXPERIMENTAL DETAILS

B.f. Equipment Diagram& Parts List

A detailed parts diagram of the recovery system combined with a block

diagram of the plasma reactor region is depicted in Figure B-2. The length, width,

and height are the nominal internal dimensions of the chamber reactor. The

chamber volume, Vc, includes volumes of protuberances of the interior of the

plasma chamber and was measured to an accuracy of 1 cm. The surface area

is the internal surface areas of all metallic protuberances and each dimension

was measured to an accuracy of 1 cm.

The recovery system volume, VR = 0.0071 m3, was determined by

expanding a quantity of gas at pressure pc from the plasma chamber (volume

V=) into the combined voiumes (VcR = VC + VR) and pressure pcF7and using

Boyle’s law, pcVc = pcRVcR. Since both pressures were measured, Vc is known,

the moles of gas remains constant before and after expansion, and temperature

remains constant, VR is calculated from:

~R _ Pcvc y_— . cPCR

(B-1)

The dimensions of the powered electrode was determined from the

surface area of a 2“ diameter stainless steel hoider on which the samples were

placed. The RF antenna is shown in Figure B-1.

Fume hood linear flow rate was obtained from design specifications of the

fume hood with the window open as specified on the hood. Room air flow was

similarly obtained from building design information for exhaust air, divided by

dimensions of the room in which the experimental chamber is located.

Dimensional characteristics of the plasma system are summarized in

Table B-1. Table B-2 is a detailed parts iist of the system.

115

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Table B-1. Characteristics Of Plasma System.

Plasma Reactor Internal DimensionsLength (m), width (m), height (m) 0.047x0.047x0.049Volume (m3) 0.125Surface Area (m*) 1.623

Recovery System (mJ) 71XIO+Powered Electrode (m*) 20.3xI 04Fume Hood (ft rein-’) 145Room Air Flow (ft3 rein-’) 47500

RF Plasma Antenna

r

IStainlessSteel Rod1.50mm thi*-

PianchetteHolder

i

‘6cm —

Figure B-1. RF Antenna.

116

Page 135: LosAlamos - International Atomic Energy Agency

Plasma Chamber & Recovery System.—

‘\

-10--.—

Oa\

M’I’ _

A-------~5?-”- ~ :

m1=

“J”’” -

.. . .—---- ~w,*

““”iv)I L3Epc-Y--- “

1-+-g&?y#&=--+- ~,_-.—————

.-

1- F-

—. ———.. ---1l\ , ,..., “Od.-,’w0F.Jq -y ~ ,

I “------’” l_+-,_.,F_ pm 1----- ——.-——7-

F_—-

?F,

m. --— ,~

*S

/Fume Hood

Figure B-2. Plasma Reactor and Recovery System.

117....-

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Table B-2. Plasma System Parts List.

!plasmaSyatem_tfa&Meter i , 1b% system hmpmtes a detailedpa~ &t of the recovery system and rrta@ ~nts of fhqplasrra chanber.

3

~Al parts are ~ Corporationunless otherwise specified II{

i

\ ftem : page S PN fXmcriptiOn*:;

1 84 4030028tww,90deg 1. ________________ .. .*: 218 420002~BoredFlangew/2tappedholes 1;2a:

—. -..——1/4”toIL?’adaptor,SS 1;

3’—.-

:I@proB.%HValve If4: 122BA-00010B2B Baratrco Ressure Transducer, Type122A/10mTom 1!—.-= .

MS FtRCIC BaratronI%ess (hntrciier~!-.

5: 195 W)OOl 6utterftyVtie ,.

6a 84 403002 Eb/ ,90 dq 1:~.

50 140007 DoubleSided Flanoe.blank ,:

21. .—

66—

404002 Tee 1+

22 88 730003 %ge adaptor D31seai-wo ,:—.—23, .–.

80 720003‘Mf Nppk?,KF—.

1:——— .. —. —.. ——.. .—... ———... -—

25 Dcwnx, 1“ lDforCaldTrap.l!Ybng, we&dtoitern20 ;:—...— -.—.-.. ... . .———-—-.. -...-. -..—.- ......... .. -——

26 122BA-00010625 BaratronRessure Transducer, Typel 22A/1000Torr-’

1,...——.—.... . . . ..—. .-. =--...... . . . . . . . . . . .. . . . . .. .. . . ._, __ ,---- .—_...—._“,.,..... .. . . .... . . .. .._Ns KF-GIBWS l-channel PWdnital readout 1:...—-----.-...._.. __. _..—.—.-....—-.—.-—.._.. ... .. ... . . - .. ..—.. .—.__._,._ . ...______ .-..—.. . ....—._._4 _________ .__.

27’ 1/4”to 1/2”adaptor, SS 1—----------- . . ..— -—-. . . ... .. . ..-..---—-— .——...——28

. . ..---. —..—— -218 -__._4~~I~-.,*ed ~n9e w ~ ~pped h~s ____–– —-...-..1:

_.- ——.. ____29 tWpro SS-4H Vatue 1

30--—-—— .—-.—

195 360001’ButterfivVatve 1-j

--..———--.—.31a 62 402002 “N@e - —

;1;

33 199 431006 hblacular Sieve, CarbonTrap 1:—.34

——58 730003 FbrIw Adaptor, ti to NWO 1:

—.—— . ..- —... —- —- ——— —.35 175 310074; KF Rght Angk Valve 1

———- ——-—. ~36

—.—.—- ...-213 441117 K150 .SSflexibkehose 2.

>—.—--.———— .“... . ..—.. —. —- --- —..—..———.-—. ..--z—.37 GRX34ThermistorGauge Station 1.

—.— .——. -.. ——.-. ——Ns: GT340A ThermistorGauge 1,——36 84 724002 Tee. W

—.~

39: ~cuum purqz Akatel 1’—.. —....—. —.. .—-—-——— ——--—— -..—

+_.— ——. — ——-900 69 __,_4470~_IGW CJoss,8“ -l =* ________ 1’

901 — RF20 %wer .%p~, 13.56 M-&, 2000W, 15A 1

902——— —--.SA2080 li?athkitAntenna Tuner

—— 1:.—.-.—.—-—_—

903.———-. —-.— .— . -—. —,.-— — ..-—..--.. .. ——. -—. ....—.-.—W150 Leyboktlk)ots Blower 1. . . ,. .. . . . .. . . . ,_...-- .. . . . ___ . . . . .. .. ... . . . . . .. . . ~____ ___ .._. ..._..\

903 D30A hvbold Forewrro 1

118

Page 137: LosAlamos - International Atomic Energy Agency

B.2. Stainless-Steel Pianchettes

Twelve stainless steel type 304 substrate planchettes were machined for

holding the depleted uranyl nitrate solution and for conversion to U02. The

substrates were shaped in cylinders with an inner diameter of 1.007 cm, an

interior depth of O.t 46 cm, and a mass of 0.5370 g (Table B-3). The average

inner diameter was 1.007 cm and inner depth 0.146 cm.

Table B-3. Stainless Steel Type 304 Sample Substrates

Planchette Inner Mass (g) Height depth ThicknessNumber Diameter (mm) (mm) bottom

(mm) (mm)1 10.07 0.5389 1.82 1.54 0.282 10.08 0.5398 1.81 ‘i .43 0.383 10.05 .0.5348 1.82 1.47 0.354 10.07 0.5387 1.80 1.46 0.345 10.07 0.5401 1.82 1.46 0.366 10.03 0.5366 1.82 1.57 0.257 10.09 0.5334 1.80 1.56 0.248 10.03 0.5362 1.81 1.47 0.349 10.07 0.5365 1.81 1.51 0.3010 10.09 0.5387 1.82 1.41 0.4111 10.08 0.5347 1.82 1.35 0.4712 10.06 0.5388 1.81 1.32 0.49

Average 10.07 0.5373 1.81 1.46 0.35Average Deviation 0.02 0.0019 0.01 0.06 0.06

The average internal surface area of the pianchette is 0.796 * 0.003 cm2

is based on the average diameter, 1.007 Y 0.003 cm.

Following the many experiments, planchette number 1 was again

characterized to account for changes in its dimensions for the UOZ density

determination. Its empty weight had increased to 0.5867 g with an inner depth of

1.34 mm. Its inner diameter had not changed.

8.3. Pressure & Flow Characteristics

The plasma reactor is a cubic aluminum chamber whose volume is

approximately 0.125 m3. It has an inlet gas line, an outlet line to the recovery

119

Page 138: LosAlamos - International Atomic Energy Agency

system, and power-input leads. System pressure is affected by the gas flow rate

and power applied. The outlet conditions are fixed by the recovery system

pumping characteristics: This section presents details of the flow renditions

inside the reactor and recovery system, description of the mass continuity

equations, the calibration of the inlet flow rotameter, the recovery system pump

characteristics, the pressure in the reactor, and finally the reactor pressure and

effect of power on the pressure.

B.3. 1. Continuity Equation

Characterization of the plasma reactor and recovery system in terms of

pressure and flow of gaseous products is determined from the mole balance (or

mass balance) equation of continuity. Consider a chamber whose volume, V,

contains a gas at a pressure, p, with an inlet flow of FOmoles of gas per unit time

and an outlet flow of F moles per unit time. The applied RF power causes some

of the gas to dissociate and others to recombine for a net molar production rate,

G. The mole balance then becomes

(B-2)

The partial derivative is the accumulation of moles, q, in the chamber over

time, t. This section describes conditions for the gas inlet properties, the exhaust

properties, and the plasma reactor characteristics.

B.3.2. inlet Conditions (Rofameter Calibration)

The rotameter, Omega model S04-N082-03, was calibrated by bleeding

NFs gas into the plasma reactor at constant rotameter settings and inlet pressure

of 20 psig. All valves between the NFs gas supply and the vacuum chamber

were fully opened, except the rotameter valve which was adjusted as necessary

to maintain the desired flow, during these experiments. By measuring the

pressure increase with time in the reactor, the fiow parameters may be

determined. With the outlet valve to the pump closed, F = O in Equation (B-2),

and pressure builds up in the chamber as gas flows in. With no power, the temn

G is also zero and hence the mole balance equation becomes

120

Page 139: LosAlamos - International Atomic Energy Agency

(B-3)

~ Applying the ideal gas law (pV = qRT) and differentiating q leads 10

V dpFO= ——

RT dt(B-4)

Because the temperature rise in the reactor is near room temperature for

the conditions of this experiment, T is taken to be constant. R is the gas

constant (8.3144 J mol-l tC1). Since the number of moles is the ratio of mass, m,

of gas to its molecular weight, M, the mass flow rate becomes

dm W dp—=— — (B-5)dt RT dt

To determine the volumetric flow rate, consider a smali volume, Vf,

containing mass m of material and calculate how fast this volume passes a given

plane. Since the same gas is used, its density is p which is constant over time

and its mass is the density times Vf. Hence, from Equation (B-5),

dV1 .l?Mdp=Vdp—— —— (B-6)T pRT dt p dt

An industry standard is the SCCM, standard cubic centimeter per minute,

at one atmosphere. The mass flow rate must be the same at one atmosphere

and at the pressure p. Then from Equation (B-5), with subscripts O for the flow

rate at one atmosphere and no subscript for the reactor interior at pressure, p,

(Figure B-3)

Plasma Chamber

‘ro

1Jnlet

Figure B-3. Inlet and Reactor Conditions

121

Page 140: LosAlamos - International Atomic Energy Agency

dVf

)

Mp Wf = g- dvf . _P_ WfStaff=— —— — —

dt ~= poRT dt pO dt p. dt(B-7)

The time-pressure data at constant rotameter settings (measured in

centimeters) was determined experimentally and the pressure data differentiated

to yield the volumetric flow rate (cm3/s), mass flow rate (g/s), and SCCM. These

results were compared to the manufacturer’s correlation (Omega, 1995) in

Equation(B-8).

r(Sccwl = ~, T Po——Scciki ~ p“

in the above equation, ps is the

at standard conditions, T and p’ are the

(B-8)

specific gravity of NF3 relative to air (=1)

temperature and pressure at the outlet of

the flow meter, and the O subscript are conditions at standard conditions (298K

and 1 atm). As an approximation, the reactor pressure p and the flow outlet

pressure p’ were assumed equal.

Figure B-4 summarizes the experimental data and the manufacturer’s

correlation data. In (a), the mass flow rate is plotted against the reactor

pressure for rotameter settings of 20, 50, 100 and 150 cm. These results

indicate that the mass flow rate is independent of pressure in the range

examined and range from 0.08 to 2.2 mg/s. In (b), the data are transformed to a

flow rate at the reactor pressure. The flow rate existing in the reactor is found to

obey an exponential law, decreasing with increasing pressure. When this data is

converted to standard temperature and pressure (c), the SCCM are constant

with pressure and range from 1.7 to 44.2 SC(2M. The manufacturer’s SCCM

calibration correlation (equation (B-8)) is shown in (d) with

functions varying as the square root of the pressure.

From the above data, a plot of the mass flow rate

the data fitted with

and SCCM versus

rotameter setting can be generated to compare experimental data for the

calibrated flow and the manufacturer’s correlation (B-2). Below approximately 90

to 100 cm rotameter settings, both the manufacturer’s correlation and

122

Page 141: LosAlamos - International Atomic Energy Agency

experimental calibration data

rotameter settings, where the

pressure are equal, does the

are in fairly good agreement. Only at higher

assumption that the reactor and rotameter outlet

comparison sta~ to diverge. Since most of the

experimental data were taken at and below 100 cm, then either the

manufacturer’s correlation or the experimental data calibration may be used.

123

Page 142: LosAlamos - International Atomic Energy Agency

(a) Inlet Mass Flow Rate (NF3) lRotameter Model: S04-N082-031 (c) SCCM (NF3)

RF Power= OW100

1-10 100

Pressure (Pa)(b) inlet Volumetric Flow Rate(NF~)

105

\D o 20cm

1040 50cmv 1OOcm

&

● 150cm

103

dVldt = ae b)

I n2 b“ BOUIWJCnllbmlkm)ds“ibw.in-a~,“

1 10 100 1000

Pressure (Pa)tlmwcmdiionseqbmfg wpg

4419SCCM

18.09SCCM

ccm4n WI SC4JI-C4Calw’atim.lds“ilOwn.d1 10 100 1000 10000

Pressure (Pa)(d) Manufacturer’s Flow Meter Data (NF3)

i

10 20 30 40

Pressure (Pa)

Figure B-4. Experimental & Manufacturer’s Flow Calibration Data

124

.-

Page 143: LosAlamos - International Atomic Energy Agency

0.0025 “

0.0020 :~ ‘ :

0.0015 ‘ -Z ,()

0.0010

0.0005

“20

“ 10

OL u Jo 50 100 15:

Rotameter Flow Setting, F (cm)

Figure B-5. Rotameter Gas Flow Calibration

B.3.3. Recovery System Characteristics

The recovery system measures -7.1 Las determined by the expansion of

NF3 gas into the volume. It is constructed with 2.75” Conflat flanges and pipes

measuring approximately 1” internal diameter. The recovery system contains

liquid nitrogen and activated charcoal traps and an Alcatel forepump, model

201 2A. The purpose of this section is to characterize the pumping

characteristics of the recovery system.

The flow ranges from the intermediate to the viscous regime in the

recovery system with Knudsen numbers ranging from 0.016 at 10.8 Pa to 0.004

at 40 Pa for a 1” pipe. Thus, diffusion limited flow is expected for most of the

pressure range considered.

In determining the pumping characteristics, a volume of gas was fiowed

into the plasma reactor until an initial pressure (about 11 Torr) was achieved with

the outlet valve closed. At time t = O, the outlet valve was opened. Since the

125

Page 144: LosAlamos - International Atomic Energy Agency

inlet valve is closed, FO= O and with no RF applied, G = O. Hence, the mole

balance equation (B-2) becomes

4’“-F=% (B-9)

From the ideal gas law, equations (B-4), (B-5), and (B-6) apply for the

mole flow rate, the mass flow rate, and the volumetric flow rate, respectively, with

F replacing Fo.

The throughput, Q, is obtained from the expression

(B-1O)

Q is expressed in Pa-m3/s and for an isothermal system is a constant

throughout the system (Roth, 1982). With the plasma temperature of neutrals

and ions approximately constant near room temperature, the isothermal

approximation holds. Q is related to the conductance and pressure differential

between the plasma reactor (p) and the pump inlet (pI) by

Qc=— (B-n)@

4P= P-PI (B-12)

To obtain the outlet flow characteristics, two readily available gases, Nz

and NF3, were used. These gases, with molecular weights of 28 and 71 g/mole

respectively, provide a spread of values to assess the variation with molecular

weight. In this approach , the plasma reactor was flooded with the gas to a

pressure in excess of 11 Torr. At t = O, the outlet valve was opened and the

reactor pressure versus time measurements taken. The pressure measurement

errors are largest immediately after opening the valve, but as the flow stabilized,

accuracy was to within 1 mTorr.

The results of this experiment are shown in Figure B-6. In (a) the NF3

mass flow rate and volumetric flow rate (in SCCM) is shown over the range of

pressures measured. In the 10-50 Pa used for the majarity of the plasma

126

Page 145: LosAlamos - International Atomic Energy Agency

etching experiments, the mass flow rate ranges from 0.15 mg/s to 1.6 mgls (3 to

34 SCCM). In (b), the NF3 throughput Q ‘and the volumetric flow rate at the

reactor pressure are shown. The throughput ranges from 0.04 to 0.42 Pa m3 S-l

and the volumetric flow rate from 550 to 1400 cm3/s from 10 to 40 Pa. In (c) and

(d), the N2 parameters are shown. Mass flow rate in the range 10-40 Pa range

from 0.1 mg/s to 1 mg/s, flow rates range from 3.7 to 50 SCCM, throughput form

0.07 to 0.6 Pa m3 S-l, and volumetric flow rates from 575 to 1900 cm3/s.

The conductance calculation had to be approximated because it relies on

the pressure differential between the plasma reactor and the recovery system

pump inlet. The pump inlet gauge was no longer operational during these

experiments, so the data used was that obtained during plasma operation at the

time the gauge was operational. Consequently, the exiting gas is actually a

mixture of various species, more closely approximating NF3 molecular weight

based on CHEMKIN results. The data for the variation of pressure differential

versus plasma reactor pressure is shown in Figure B-7 (a) and the correlation is

fitted with a straight line through zero with a slope of 0.8036.

Applying the above pressure correlation to equation (B-11) with the Q

values calculated for NF3 and N2 yields a conductance that is only weakly

dependent on the species, as shown in Figure B-7 (b). The correlation listed

was for with NF3 data.

The conductance correlation was subsequently applied to the plasma etch

data to determine the mass and volumetric flow rates. From equations (B-6),

(B-1 O), and (B-12), the volumetric flow rate may be calculated from the

relationship

(B-13)

The experimental values of the mass flow rate and the volumetric flow

rate measured during plasma etching operations calculated using the mass flow

rate and conductance correlations and the appropriate flow equations. These

127

Page 146: LosAlamos - International Atomic Energy Agency

are plotted in Figure B-6(a) and (b) for the mass flow rate and the volumetric flow

rate. As can be seen, the data points fall on the NF3 measured flow rates.

128

Page 147: LosAlamos - International Atomic Energy Agency

(a) NF3Exhaust Flow Rate

ldrn/dt= +5.32E-71)2+1.92E-5$ -6.08E-5~!0015 .

0010 -

0 0+15- - 1(72

o0 xl m

Pressure(Pa)

(b) NF, Exhau?il Flow Rate

)

//

/

“o 50 100Preswm (Pa)

recOvery-flow-nf3- n2 .epg

Figure B-6. Recovery

1030

Imo

!Wo

,Wm

I

(c) N2 Exhaust Flcyi Role0.05

0,04-

g - 1500

[

4

0,01 - - w

o0 20Q 401 aoo me

Pressure (Po)

(d) N, Exhaust Flow Rete

4- 0~.- ----- ---n -.---4W0

~-“ 30W‘E ~ .

#

E .;’Do

4 m

“a

o. moo

o~

2a2 400 m 404 10APmssum (Pa)

System Flow and Throughput Characteristics

Page 148: LosAlamos - International Atomic Energy Agency

Pressure Differential Between Chamber & Pump Inlet

40

y=ax max dev:3.96, ?=0.949a=O.8036

0/’ [email protected] I : I ! 10 10 20 30 40 50

Chamber Pressure (Pa)

5

1

f)

conductance Of Recovery System

C = -5.53E-5x2+0.0377x1+0.2.28

“o 50data.amductance-rt3-n2.epg

Figure B-7. Recovery System

100 150 200Pressure (Pa)

Pressure Differential & Conductance

130

Page 149: LosAlamos - International Atomic Energy Agency

B.3.4. Pressure In Reactor

During plasma processing, pressure and flow conditions within the plasma

eventually reach a steady state value. At steady state, the accumulation of

moles of gas in the chamber approaches zero. Thus, the mole balance equation

becomes

FO– F+G=O (B-14)

The net molar production rate, G, is made up of two sources: the bulk

volume species production and heterogeneous surface reactions that contribute

to the gas phase species.

G=~JrjdV+$Z*fijda (B-15)

J

The above function includes ~,the reaction rate of the ~ species; dV, the

elemental volume element i, the outward unit normal vector from the sutiace;

~,, the flux of species j from the sutiace; and da, the elemental surface

element. The volume integration (bulk volume term) is throughout the plasma

volume, the surface integration (heterogeneous term) is on all surfaces exposed

to the plasma, and the sum is over all species. When RF power is applied, NE

molecuies are dissociated into many species, including ions, radicals, and other

neutrals while sutiace losses will reduce the net formation of the plasma species.

Fluorination of solid U~ samples will release UFG into the gas phase according

to equation (B-16). For every mole of U@ reacted on the surface with 6 moles

of F atoms, one mole each of UF6 and 02 will desorb into the gas phase, for a

net loss in the gas phase of 4 moles for every mole of U~ reacted.

(B-16)

The total number of moles added in the gas phase after conditions in the

plasma have stabilized may be estimated from the ideal gas law as

(B-17)

131

Page 150: LosAlamos - International Atomic Energy Agency

Aq is the net change in the number of moles due to power increases, Ap

is the net change in pressure with RF power, V is ‘the reactor volume, and T the

temperature of the plasma (neutral gas temperature).I

In order to esfimate the bulk plasma contribution, the pressure increase

with power was measured without any uranium sample. Hence, only

contributions from the bulk plasma term are obtained, simplifyhg estimations of

contributions from UFG. The pressure rise with power for various NF flows

{rotameter settings) is shown in Figure B-8. In (a), the absolute reactor pressure

is plotted with absorbed power, showing the increase in pressure compared to

zero power. In (b) the number of moles generated in the bulk plasma is shown,

based on equation (B-17). The added contribution to the number of moles from

10.3 mg of UOp (typical sample mass) from the fluorination reactions (equation

(B-16)) can add up to 0.04 mmole of OZ and UFGto the gas phase and a loss of

0.24 mmole of F atoms, assuming a worse case that all UE and 02 remains in

the chamber.

132

Page 151: LosAlamos - International Atomic Energy Agency

u

3f

2(

1(

(

0.4

0.,m

‘o

x

Chamber Characteristics

~ Rotameter Modei S04-N082-031000 W Matching Network

v Vw uv v v v

-v

~~

-- -- ---50 100 150 ZIXJ

Absorbed Power (W)

Moles Gas Created DuringPlasma Operations

Source mtorr-pwrun.epgn

40 60 80 100pa-m01e2.epg

Rotameter Setting

Figure B-8. Effect of RF Power on Reactor Pressure

133

Page 152: LosAlamos - International Atomic Energy Agency

B.3.5. Residence Thne,r

The residence time is defined as

(B-18)

V is the chamber volume and the volumetric flow rate (d~/dt)~ is taken at

the entrance to the chamber. Note that the volumetric flow rate is NOT the

SCCM; it’s the flow rate at the given pressure obtained from equation (B-6).

From the ideal gas law equation of state (pV = qRT) with T, p, and R constant,

and differentiating this equation for the volumetric flow rate at the entrance gives

(wy (B-19)

The first form of the residence time uses equation (B-19). The second

form of residence time uses the entrance volumetric flow rate written in terms of

SCCM using equation (B-7) with POthe pressure at one atmosphere. The third

form uses the gas density p in the plasma and the inlet mass flow rate, tie.

pv vr— L–d’ ($-20)= FORT= (sCC~) PO me

B.3.6. Effect Of Power On Pressure

For a given rotameter flow setting with the recovery system rotary pump in

operation resulted in set pressures dependent on the operating power. These

results are shown in Figure B-9.

134

Page 153: LosAlamos - International Atomic Energy Agency

50

40

30

20

10

r)

❑ ✛ oe .1c1 14

v 24

●oA ‘; “1 AZ!?100

I

a-,.-

Es ..-

J

Rotameter Model: S04-N082-03

{

+ 168 Ae 21OWAbsorbed ~

-o 40 80 120

Rotometer Flow Head (cm)

Figure B-9. Rotameter Setting During Plasma Operation

13.3.7. Plasma Extinguishing Pressure

A plasma cannot be ignited at too low pressure (below about 0.7 Pa) nor

at high pressure. The extinguishing high-pressure plasma value was determined

by experiment, using as criteria a zero DC sheath voltage. The results are

summarized in Figure B-1 O. An initial charge of NF3 gas was introduced inside

the plasma chamber and then all inlet and outlet valves were closed. The lower

cufve in the figure shows this pressure level. Then, for each power, the pressure

increase that results with power application was determined (second curve).

Next, the NF3 gas inlet valve was opened until the extinguishing pressure was

found (top cume). The extinguishing pressures were found to vary from 105 Pa

at 38.5 W to 272 Pa at 168 W.

135

Page 154: LosAlamos - International Atomic Energy Agency

““1000 ~

100

10

Outlet valve to pumps is closedCriteriaFor Etitnguished Plasma is aSheath Voltage = 0.0 achieved byflowing NFqgas until plasma extinguished

7’

Extinguishing Pressure

Stabilized Pressure With RF, No Flow ❑n

c1

Startin~Base Pressure, No Power, No Flow

m%a am-50 100 150

Absorbed RF Power (W)

Figure B-1 O. Plasma Extinguishing Pressure

8.3.8. Knudsen Flow

In the range of pressure used, p = 10.8 to 40 Pa, the reactor chamber was

in the viscous flow regime with a Knudsen number, Kn, below 0.01 and transport

was therefore diffusive (Roth, 1982). The Knudsen number in these experiments

is related to the NF3 molecular diameter, d, the mean free path, k, the

temperature, T, and the pressure, p. Using a hard sphere approximation to

calculate d (Alberty, 1997) with the viscosity, v, equal to 0.0183 mPa-s (13raker

and Mossman, 1980) gives an NF3 molecular diameter of 4.61 xl 010 m. Applying

the ideal gas law to calculate 1 provides the relationships to calculate Kn. The

relationships are shown below.

d/[1

5 kTM 1’2——= 16v fl~ ‘

(B-21)

(B-22)‘=&’136

Page 155: LosAlamos - International Atomic Energy Agency

KJ2=A (B-23)d“

The Knudsen values for the experimental chamber Figure B-1 1) are.:

compared for different characteristic lengths to include the plasma reactor (0.5

m), a 1” diameter pipe, and the sheath thickness (-0.5 cm). For the pressure

(10.8 to 40 Pa) and temperature (-298K) range of the plasma, molecules

traversing the sheath are in the intermediate flow regime, that is, they will suffer

one or more collisions. Molecules traversing the reactor chamber are in the

viscous regime and will suffer many collisions. Molecules traversing a 1” pipe

will vary from the intermediate to the viscous regime.

10000

100

1

0.01

0.00010

t

Molecular Flow

L .—. — Li—-—.—-—- -—--

40 20 30 40

‘1Intermediate Flow

-—- -— --

v

Pressure (Pa)

Figure B-1 1. Type of Flow in Plasma Chamber.

137

Page 156: LosAlamos - International Atomic Energy Agency

APPENDIX C. DATA

C.1. Experimental Data

Table C-1 contains the depleted uranium oxide plasma processing data,

It contains only data during which the sample was continuously immersed in

plasma. Each sample contained 100 microliters of uranyl nitrate hexahydrate

solution pipetted into a 1.007 cm diameter stainless steel planchette which was

subsequently converted to UOZ by heating and flaming.

C.2. Table Abbreviations

The abbreviations and definitions used in the Table C-1 headings are as

follows:

ID

t (rein)

Flelative error, t

AbsorbedPower (W)

TransmittedPower (W)

Pressure (Pa)

NF3 Flow (cm)

Sheath (V)

Dilution Factor

Identification number

Plasma process time, in minutes, adjusted by 7 minutes toaccount for the delay in the plasma reaching operatingconditions.

The relative error in plasma immersion time.

Power absorbed by the plasma in watts.

Power transmitted (output of the RF-20 power supply) in watts.

Pressure in the plasma chamber during operation and aftersteady state has been reached, in Pascal.

The rotameter head indication in centimeters is indicative ofthe gas flow to the chamber.

Effective DC plasma sheath potential in volts. Because mostof the voltage is dropped in the powered electrode sheath, thisvoltage is effectively the voltage across the powered electrodesheath.

The ratio of either the total volume or mass of the sample tothe corresponding volume or weight of the aiiquot counted indeterrninina the activitv.

138

Page 157: LosAlamos - International Atomic Energy Agency

ID Identification number

Relative ErrorDilution

Alpha Detector(Ca) (cpm)

Alpha 2cJ (%)

C(t) (cpm)

Relative Errorc(t)

A(t) (dpm)

Relative errorA(t)

~ (dpm)

NR

Relative Error in

NR

Etch Rate

(ym/min)

The relative uncertainty in measuring the dilution of the washfor counting purposes. Significant changes during course ofthe experiments attributed to improved procedures.

The count rate (counts per minute) measured by the liquidscintillation. All reported values include curve fitting the alphapeak with a gaussian and first order polynomial, andintegration of the gaussian to determine this value.

The two sigma uncertainty determined by Poisson countingstatistics, expressed as a percent. This value is determined

r

~cazc where ~ is the counting time, generally 60as 200C=tc

minutes.

The count rate (counts per minute) corrected for alpha/betaparticle mislabeling.

The relative error in C(t).

The true activity remaining on the sample following plasmaimmersion, in disintegrations per minute.

The relative error of the activity.

The initial activity on a sample, prior to plasma immersion(disintegrations per minute). This value is not shown on thechart and is equal to 7764 dpm for the sampies used.

‘(t) it represents the amount of activityThe ratio 1– —.AO

removed from the sampie, normalized to the initiai activity.

The reiative uncertainty in k.

The U02 etch rate calculated from the experimentaiiydetermined density (4.8 g/cm3) as given in Appendix E from

the relationship[1

Mk2f4 NR

@N~ in(2) t

139

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C.3. Depleted UOZ

Table C-1. Depleted UOZ Experimental Data

TransrnMed Press. NF3Flow(cm)

50505050505050505050505050505050505050505050505050505050

50

50

50

Sheath(v)

-45-46-46-46-44-44-45-45-45-45-45-45-126-128-127-127-130-130-136-136-134-134-134-134-140-140-140-444

-139

-36

-38

DilutionFactor

Rel.Error

dilution

AlphaDetectof

(cd(:q{)

369180191223196655362342735189165130?775036121155298345322310000

6415

2551

5444

5329

Alpha20 (70)

2.532.693.653.733.463.692.603.533.274.414,964.393.764.024.533.883.644.284.704,142.992.782.882.930.000.000.000.32

0.51

0.35

0.35

c(t)(cpm)

Rel. A(t) Ret. NR Rel. EtchRateError (dpm) Error Error (@rein)

ID

45910111213151618192026272629303132333435363736394045

49

80

81

(Jin)Rel, Absorb

error, t Powerw)

0011 49.60.011 49.60.006 49.60.008 49.60.005 49.60.005 49.60.003 49.60.002 49.60,002 49.60.001 49.60.001 49.60.001 49.60.004 49.60.004 49.60.033 49.60.033 49.60.001 49,60.001 49.60.002 49.60002 49.60.006 49.60.008 49.60.017 49.60.0’!7 49.60.000 49.60.000 49.60.000 49.60.011 49.6

0.003 49.6

0.002 0.1

0.002 0.1

Power(w)

120120120120120120120120120120120120120120120120120120120120120120120120120120120120

120

23.9

23.9

(Pa)c(t) A(t) NR

15.715.616.416.416.116.116.716.716,716.716.716.716.016.016.516.516,516.516.016,016.516.517.217.217.117.117.117.3

17.9

16.0

16.0

16.6019.0035.0035.0021.0021.0040.0040.0040.0040.0040.0040.0022.5723.2926.2916.0027.43240019.4316.0017.7115.1420.2921.2912.434.804.601.03

0.0510.0450.0280.0280.0410.0410.0260.0260.0260.0260.0260.02600300.0290.0270.0390.0260.0290.0340,0390.0360.0410.0330.0310<0490.0450.046

5.544E-05

5.272E-05

5,338E-05

4,632E-

41336417718821919f8351603225331851621271734833116150294340316307000

6334

0.0190,0200.0220.0210,0220.0230,0260,0350.0330.0470.0530.0450.0220.0230.0230.0250.0420.0560.0310,0290.0210.0210.0200.0190,0070.0070.0080.019

6855691062006590459440203311204523941284fool130141643776335027651304601225824055204514164526527

000

0.056

0.0520.036

0.0380.0490.0500.0400.0460,0440.0550.0610.0540.0400.0400.0380.0490.0520.08600480.0510.0440.0480.0410.0400.0520.0460.0490.025

0.1170.1100.2010,15104080.4820.5740.7370.6920.8350.8710.8320.4610.5140.5690.6440.8320.8970.7090.6900.3300.3380.1690.1591.0001.0001.0000.162

0.5590.5710.2440.3440.1000.0740.O460.02400290,0150.01f0.0150.0730.0590.0470.0380.0140.0090.0280.0320.1330,1340.3110.3290.0070.0070,0080.280

3.57E-013.35E-013.76E-012.84E-013.55E-014.20E-013.25E-012.85E-012.68G01,1.80E-011.86E411.80E-012.96E-013.29E-012.61E-012.98E-O?1.79E-011.93E-012.06E-012.03E-015.74E-015.68E-011.37E+o01.29E+O0

-.1.70E-021.70E-021.70E-024.93E-01

8813132826436363113113113383853531131138383141433

143314331433

8

53

84

1.167

1.11

2382 0.047 2779 0.050 0.642

0.240

0.039

0.177

2.95E-01

5320

5218

0.024 5903 0.028 6.95E-02

7.77E-021.09 0.023 5685 0.028 0.268 0.15284

140

Page 159: LosAlamos - International Atomic Energy Agency

ID

82

83

84

85

86

87

89

109

112

113

117

120

121

122

123

124

125

129

130

(iin)

53

53

23

23

68

68

38

113

83

83

53

53

53

53

36

38

38

8

8

Rel. Absorb TransmittedPress.error, t Power

(w)

0,003 0.1

0.003 0.1

0.006 0.1

0.006 0.1

0.002 0.1

0.002 0.1

0.004 0.1

0.001 49.6

0.022 49,6

0.022 49.6

0,003 49.6

0.033 212.6

0.033 212.6

0.033 212.6

0.044 212.6

0.044 212.6

0.044 212.6

0.133 212.6

0.133 212.6

Power (Pa)(w)

23.9

23.9

23.9

23.9

23.9

23.9

23.9

120

120

120

120

500

500

500

500

500

500

500

500

16.4

16.4

16.3

16.3

16.7

16.7

16.4

17.9

18.1

16.1

17.9

18.0

18.0

18.0

18.1

18.1

18.1

18.4

18.4

Table C-1. Depleted UOZ Experimental Data

NF3Flow

50

50

50

50

50

50

50

50

50

50

50

50

50

50

50

50

50

50

50

Sheath(v)

-21

-21

-30

-30

-20

-20

-31

-139

-133

-133

-136

-405

-405

420

-420

-398

-398

Dilution Rel. Alpha Alpha c(t) Rel. A(t) Ret. NR Rel. EtchRateFactor Error Detector 20 (%) (cPm) Error (dpm) Error Error (wrtlmin)

dilution

051.02 4.765E-

051.02 4,768E-

051.07 4.508E-

051.07 4.466E-

051.01 4.670E-

051.01 4.817E-

051.03 4.532E-

051.10 4.476E-

051.06 0.000E+

001.1,1 0.000E+

001.11 4.396E-

051.11 4,441E-

051,17 4.245E-

051.07 4.517E-

051.08 4.483E-

051.00 4.744E-

051.07 4.543E-

051.03 4.575E-

051.05 4.553E-

05

(cd(cpm)

6972

7100

6367

6665

6899

6361

6574

393

2709

2559

2869

116

60

81

120

407

190

3055

3281

c(t)

0.31 6878 0.020

0.31 7005 0.020

0.32 6241 0.023

0.32 6554 0,021

0.31 6791 0,021

0.32 6239 0.022

0.32 6469 0.021

1.30 195 0.529

0.50 2558 0,041

0.51 2411 0.043

0.48 2715 0.040

2.06 0 0.001

2.60 0 0.001

2.34 0 0.001

2.36 0 0!001

1.28 186 0,617

1.67 0 0.001

0.47 2834 0.051

0,45 3099 0!041

7044

7179

6670

7036

6868

6266

6651

215

2713

2682

3026

0

0

0

0

186

0

2913

3246

A(t) NR

0.025 0.093 0.530

0.025 0.075 0.664

0.027 0.141 0.337

0.026 0.094 0.529

0.026 0.115 0.418

0.027 0.190 0.235

0.026 0.143 0.326

0.529 0.972 0.015

0.044 0.651 0.035

0.045 0.655 0.035

0043 0.610 0.041

0.015 1.000 0.001

0.015 1.000 0.001

0.015 1.000 0.001

0.015 1.000 0.001

0.617 0.976 0.015

0.015 1.000 0.001

0.053 0.625 0.043

0.044 0.582 0.047

.

4,26E-02

3.46E-02

1.49E41

9.94E-02

4,14E412

6.62E-02

9.20E-02

2.1OE-O1

1.91E-01

1.92-E-01

2.61E-01

4.60E-01

4.60E-01

4.60E-01

6.41E-01

6.26E-01

6.41E-01

1.90E+O0

1.77E+O0

141

Page 160: LosAlamos - International Atomic Energy Agency

ID

131

140

141

442

143

144

147

148

149

152

153

154

155

156

157

158

159

160

161

162

(N/in)

6

53

53

53

53

53

53

53

53

53

53

53

53

53

53

53

53

53

53

23

Ret. AbsorbTransmittederror, t

0.133

0.033

0.033

0.033

0.033

0.033

0.033

0.033

0.033

0,033

0.033

0.033

0.033

0.033

0.033

0.033

0.033

0.033

0.033

0.067

(w)

212.6

42.8

42,8

41.4

39.4

39.4

41.4

41.4

40.3

39.2

39.2

44.6

44.6

39.6

39.6

44.7

44.7

40.3

40.3

23.7

Power

w)

500

100

100

100

100

100

100

100

100

100

100

100

100

100

100

100

100

100

100

72

Press.(Pa)

16.4

7.9

7.9

32.4

25.7

25.7

10.5

10.5

13.6

22.0

22.0

5.7

5.7

16.4

16.4

38.4

38.4

29.6

29.6

16.4

Table C-1. Depleted UOZ

NF3Flow(cm)

50

20

20

100

75

75

30

30

40

65

65

10

10

50

50

120

120

90

90

50

Sheath(v)

-398

-172

-172

-18

-66

-66

-153

-153

-135

-64

-84

-183

-183

-117

-117

-14

-14

-38

-38

-79

DilutionFactor

1.01

1.08

1.24

1,00

1.10

1.06

1.05

1.01

1.27

1.07

1.08

1.17

1,14

1.01

1.00

1.01

1.02

1.10

1,06

1.05

Rel.Error

dilution

4,630E-05

4.526E-05

4,285E-05

4,051E-05

4.352E-05

4.391E-05

4.558E-05

5.271E-05

4.264E-05

4,532E-05

4.525E-05

4.367E-05

4.432E-05

4.71$E-05

5.083E-05

4.927E-05

4.701E-05

4.494E-05

4.536E-05

4,590E-

Experimental Data

Alpha Alpha c(t)Detector 20 (%) (cPm)

(c.)(cc;)

6031

5069

4582

4793

5139

5857

6201

4369

5320

5001

6239

5860

5371

5752

5271

4436

4498

5689

0.44 3222

0.33 5940

0.36 4981

0.38 4411

0.37 4655

0.36 4999

0,34 5764

0.33 6106

0.39 4297

0.35 5176

0.37 4846

0.33 6166

0.32 6626

0.34 5738

0.35 5212

0.34 5564

0.36 5070

0.3677 4252

Rel.Errorc(t)

0.039

0.021

0.021

0.032

0.027

0.026

0.021

0.021

0.023

0.026

0,028

0.019

0.018

0,023

0.027

0.029

0.032

0.034

A(t)(dpm)

3262

6385

6179

4430

5119

5301

6036

6162

5453

5561

5242

7245

7556

5780

5238

5615

5151

4686

Ret.ErrorA(t)

0.042

0.025

0.026

0.035

0.031

0.030

0.026

0.025

0.028

0.030

0.032

0.024

0.024

0.028

0.031

0.033

0.035

0.037

NR

0.580

0.176

0.204

0.429

0.341

0.317

0.223

0.206

0.298

0.284

0.325

0.067

0,027

0.256

0.325

0.277

0.337

0.396

Rel. EtohRateError (pm/mIn)NR

0.046 1.77E+O0

0.252 8.17E-02

0.214 9.39E-02

0.079 1.97E-01

0.111 ‘- 1.57E-01

0.122 1.46E-01

0.191 1.02E-01

0,210 9.49E-02

0.131 1.37E-01

0.144 1.30E-01

0.120 1.49E-01

0.751 3.07E-02

1.951 1.23E-02

0.162 1.18E-01

0.119 1.50E-01

0.152 1.27E-01

0.118 1,55E-01

0.092 1.82E-01

0.385 4311 0.034 4557 0.037 0.413 0.086 1.90E-01

0,34 5566 0.022 5867 0.027 0.242 0.172 2.56E-01

142

Page 161: LosAlamos - International Atomic Energy Agency

Table C-1. Depleted U02 Experimental Data

ID

163

164

165

166

167

169

170

171

172

173

178

179

204

205

206

207

208

209

210

(N/in)

23

63

83

83

83

23

53

53

53

53

23

23

53

53

53

53

83

83

23

Ret. Absorb Transmittederror, t Power

(w)

0.067 23.7

0.022 102.4

0.022 102.4

0.022 23.7

0.022 23.7

0.067 102.4

0.033 23.7

0.033 23.7

0.033 102.4

0.033 102.4

0.006 49.6

0.006 49.6

0.033 96.1

0.033 96.1

0.033 103.4

0.033 103.4

0.022 26.5

0.022 26.5

0.067 26.5

(w)

72

240

240

72

72

240

72

72

240

240

120

120

240

240

240

240

72

72

72

Press(Pa)

16.4

17.1

17.1

16.3

16.3

17.2

16.1

16.1

17.5

17,5

16,7

16.7

10.9

10.9

30.3

30.3

10.9

10.9

11.1

NFsFlow(cm)

50

50

50

50

50

50

50

50

50

50

50

50

30

30

80

80

30

30

30

Sheath(v)

-79

-292

-292

-104

-104

-290

-103

-103

-266

-286

-170

-170

-273

-273

-185

-185

-116

-116

-115

Dilution Rel. Alpha Alpha c(t) Rel, A(t) Rel. NR Rel. Etch RateFactor Error Detector 2U (%) (cPm) Error (dpm) Error Error (umlmin)

dilution

051.06 4.502E-

051.03 4.724E-

051.03 4.762E-

051.03 4.567E-

051,02 4,617E-

1.07 4.4T3E.05

1,09 4.466E-05

1.10 4,473E-05

1.12 4.464E-05

1.06 4.491E-05

1.09 4.524E-05

1.08 4.504E-05

1.00 4.609E-05

1.01 4.500E-05

1.01 4.696E-05

1.02 4.486E-05

1.02 4.643E-05

1.04 4.566E-05

1.01 4.877E-05

(Ca)(cpm)

5771

1371

767

5365

4725

3403

5442

5556

650

1647

5665

5348

3010

2256

192

220

6272

6015

7238

c(t) A(t) NR

0.34 5678 0.021 6107 0.026 0.213 0.201

0.60 1177 0.095 1213 0.096 0.844 0.020

0,93 566 0.192 580 0.192 0.925 0.016

0.35 5243 0.024 5386 0,028 0,306 0.127

0.36 4589 0,027 4675 0.031 0.398 0.087

0.44 3234 0.038 3462 0.041 0.554 0.051

0.35 5303 0.026 5780 0.030 0.256 0.165

0.35 5420 0.025 5936 0.029 0.235 0.183

0.69 649 0.169 725 0,170 0,907 0.018

0.64 1452 0.079 1574 0.061 0.797 0.024

0.3424 5552 0.024 6036 0.029 0.223 0.196

0,3531 5183 0.028 5585 0.032 0.261 0.148

0,47 2795 0.050 2804 0.053 0.639 0.040

0.54 2017 0.071 2037 0.073 0.738 0.031

1.86 0 0.001 0 0.015 1.000 0.001

1.74 0 0.001 0 0.015 1.000 0.001

0.326 6158 0.022 6250 0.027 0.195 0.227

0.3329 5896 0.023 6133 0,027 0.210 0.206

0.3035 7139 0.020 7186 0.025 0,074 0.674

2.26E-01

2.48E-01

2.72E-01

9.00E-02

1.17E-01

5.67E-01

1.18E-01

1,08E-01

4.17E-01

3.67E-01

2.36E-01

2.97E-01

2.94E-01

3.39E-01

4.60E-01

4.60E-01

5.73E-02

8.17E-02

7.89E-02

143

Page 162: LosAlamos - International Atomic Energy Agency

ID

211

212

213

214

215

216

217

218

219

222

223

224

225

226

227

228

229

230

231

232

(M’in)

23

53

53

83

83

53

53

23

23

53

53

23

23

83

83

53

53

’23

23

63

Rel. Absorb Transmittederror, t

0.067

0.033

0.033

0.022

0.022

0.033

0.033

0.067

0.067

0033

0.033

0.067

0.067

0.022

0.022

0.033

0.033

0,067

0.067

0.022

Power(w)

26.5

26.5

26.5

27.3

27.3

27,3

27.3

27.3

27.3

50.6

50.6

50.6

50.6

50.2

50.2

50.2

50,2

50.2

50.2

96.1

Power

(w)

72

72

72

72

72

72

72

72

72

120

120

t 20

120

120

120

120

120

120

120

240

Press(Pa)

11.1

10.9

10,9

32.4

32.1

31.6

31.6

31.7

31.7

11.1

11,1

11.2

11.2

35.2

35.2

35.1

35.1

35.7

35.7

10.8

Table C-1. Depleted U02

NF3Flow(cm)

30

30

30

100

100

100

100

100

100

30

30

30

30

100

100

100

100

100

100

30

Sheath(v)

-115

-111

-111

-9

-9

-8

-6

-8

-8

-179

-179

-177

-177

-18

-18

-20

-20

-36

-36

-325

DilutionFactor

Rel.Error

1.02

1.00

1.01

1.01

1.01

1.03

1.01

1.07

1.03

1.00

1,00

1.00

1,00

1.01

1.00

1.01

1.01

1,00

1.00

1.00

4.621E-05

4,660E-05

4,547E-05

4.710E-05

4.612E-05

4.563E-05

4.628E-05

4.503E-05

4.597E-05

4.670E-05

4.568E-05

5.021E-05

4.515E-05

4.586E-05

4.599E-05

4.362E-05

4.625E-05

4.818E-

4.;7E-05

4.455E-

144

Experimental Data

Alpha Alpha c(t) Ret.Detector 2CI (%) (cpm) Error

(ccl) c(t)(cpm)7062 0.3068 6978 0.020

6510 0.32 6363 0.024

6303 0.3252 6164 0.024

7108 0.3063 6995 0.021

6326 0.3246 6163 0.024

6722 0.3149 6604 0.022

6880 0.3113 6748 0.022

6705 0.3153 6591 0,021

7313 0.3019 7207 0.020

4954 0.3668 4807 0.028

6074 0.3313 5932 0.024

6608 0.3176 6488 0.022

5537 0.347 5365 0.028

1172 0.7542 946 0.133

1456 0.6767 1239 0.100

3155 0.4596 2987 0.040

2721 0.495 2550 0,045

3710 0.4239 3538 0.036

3147 0.4602 2964 0.043

1193 0.7474 994 0.113

A(t)

7115

6386

6196

7033

6251

6809

6812

7042

7405

4827

5957

6518

5382

951

1243

3009

2566

3546

2976

999

ReLErrorA(t)

0.025

0.028

0,028

0.026

0.028

0.026

0.027

0.026

0.025

0.031

0.029

0.027

0.032

0.134

0.101

0.043

0.048

0!039

0.045

0.114

NR

0.084

0.177

0.202

0.094

0.195

0.123

0.123

0.093

0.046

0.378

0.233

0.161

0.307

0.878

0.840

0.612

0.669

0.543

0.617

0.671

Rel. Etch RateError (prn/min)

NR

0.596 8.86E-02

0.259 8.1 5E-02

0.221 9.28E-02

0.525 2.77E-02

0.231 5.72E-02

0.391 5.88E-02

0.395 5.84E-02

0.535 9.85E-02

1.120 4.90E-02

0.095 1.74E-01

0.185 1.07E-01

0.288 1.70E-01

0.131 3.25E-01

0,020 2.58E-01

0.021 2.47E-01

0.041 2.82E-01

0.034 3.08E-4M

0.052 5.75E-01

0.041 6.53E-01

0.018 2,58E.01

Page 163: LosAlamos - International Atomic Energy Agency

Table C-1. Depleted U02 Experimental Data

ID

234

235

236

237

238

239

240

241

242

243

248

249

250

251

252

253

259

260

261

(Mtin)

83

63

23

23

23

23

53

53

53

53

53

53

53

53

113

113

293

293

83

Rel Absorb Transmittederror, t Power

(w)

0.022 98.5

0.022 98.5

0.067 96.1

0.067 96.1

0.067 98.5

0.067 98.5

0.033 49.6

0.033 49.6

0,033 104.1

0.033 104.1

0.033 147.7

0.033 147.7

0.O33 179.8

0.033 179.8

0.017 102,4

0,017 102.4

0.001 49.6

0.001 49.6

0.022 102.6

Power(w)

240

240

240

240

240

240

120

120

240

240

400

400

400

400

240

240

120

120

240

Press.(Pa)

40.1

40.1

11.3

11.3

39.6

39.6

30.4

30.4

24.1

24.1

11.2

11.2

31.2

31,2

16.9

16.9

16.7

16.7

32.0

NF3Flow(cm)

100

100

30

30

100

100

85

85

65

65

30

30

80

80

50

50

50

50

85

Sheath(v)

-150

-150

-317

-317

-179

.179

-94

-94

-250

-250

460

460

-335

-335

-236

-236

.135

-135

-150

tXlution Rel. Alpha AlphaFactor Error Detector 20 (Y.). .

dilution

051,01 4.615E-

051.00 4.442E-

051.00 4.712E-

051.00 5.077E-

051.01 4.566E-

051.01 4,842E-

051.00 4.698E-

051.00 4.796E-

051.01 4.499E-

051.00 4.494E-

051.01 4.788E-

051.00 4.791E-

051,01 4.517E-

051.01 4.644E-

051.00 4.579E-

051.00 4.676E-

051,00 0.000E+

001.00 0.000E+

001.00 0.000E+

(c.)(cpm)

155

240

4274

3014

391

316

3067

2489

416

355

2061

1653

133

139

570

471

603

759

112

2.0708

1.6664

0.395

0.4703

1.3065

1.4533

0.47

0.52

1.27

1.37

0.57

0.60

2.24

2,19

1.08

1.19

1.05

0.94

2.44

c(t) Rel. A(t) Rel. NR ReL EtchRate(cpm) Error (dpm) Error Error (prnlmin)

c(t) A(t) NR

o 0.001 0 0.015 1.000 0.001 2.94E-01

24 4.559 24 4.559 0.997 0.014 2.93E-01

4113 0.032 4128 0.035 0.468 0.066 4.96E-01

2821 0.046 2833 0,049 0.635 0.039 6.73E-01

171 0.664 172 0.664 0.978 0.015 1.04E+O0

113 0,928 113 0.928 0.985 0.014 1,04E+O0

2857 0.049 2868 0.051 0.631 0.041 2.90E-01

2253

177

115

1833

1603

0

0

309

211

345

511

0

0.064

0.700

1.078

0.074

0090

0.001

0.001

0.443

0s40

0.391

0.258

0.000

2261

178

115

1845

1611

0

0

310

212

345

511

0

0.066 0.709 0.034

0.700 0.977 0.016

1.078 0.985 0.016

0.076 0.762 0.028

0.091 0.793 0.027

0.015 1.000 0.001

0.015 1.000 0.001

0.443 0.960 0.019

0.641 0.973 0.018

0.391 0.956 0.018

0.259 0.934 0.019

0.015 1.000 0.000

3.26E-01

4.49E-01

4,53E-01

3.51E-01

3.64E-01

4.60E-01

4.60E-01

2.07E-01

2.IOE-01

7.95E-02

7.77E-02

2.94E-0100

145

Page 164: LosAlamos - International Atomic Energy Agency

Table C-1. Depleted U02 Experimental Data

ID

262

263

264

265

266

269

271

272

273

274

275

276

277

279

260

281

262

285

286

287

(Mtin)

83

23

23

53

53

83

53

53

23

23

113

113

113

113

113

203

203

113

113

203

Rel. Absorb Transmitted Presserror, t

0.022

0.067

0.067

0.033

0.033

0.022

0.033

0.033

0.067

0.067

0.017

0.017

0.017

0.017

0.017

0.010

0.010

0.017

0.0!7

0.010

Power(w)

102,6

102.6

102.6

50.6

50.6

51,7

51.7

51.7

51.7

51.7

51.7

51.7

96.1

50.6

50.6

50,4

50.4

50.4

50.4

49.6

Power (Pa)(w)

240

240

240

120

120

120

120

120

120

120

120

120

240

120

120

120

120

120

120

120

32.0

31.7

31.7

10.9

10.9

40.1

39,9

39.9

40.3

40.3

40.4

40.4

11.2

11.3

11.3

34.9

34.9

34.9

34.9

17.5

NF3Flow

85

65

65

30

30

120

120

120

120

120

120

120

30

30

30

103

103

102

102

51

Sheath(v)

-150

-154

-154

-230

-230

-9

-9

-9

-9

-9

-9

-9

-272

-146

-148

-13.5

-13.5

-15

-15

-135

Dilution Rel. AlphaFactor Error Detector

dilution (Ca)(;p#

1.00 0.000E+00

1.00 0.000E+ 212100

1.00 0.000E+ 149500

1.00 0.000E+ 527100

1,00 0.000E+ 581600

1.00 0.000E+ 485300

1.00 0.000E+ 642000

1.00 0.000E+ 676400

1.00 0.000E+ 673100

1.00 0.000E+ 682700

1.00 0.000E+ 450400

1.00 0.000E+ 453200

1.00 0.000E+ 83100

1.00 0.000E+ 419800

1,00 0.000E+ 502200

1.00 0.000E+ 100700

1.00 0,000E+ 118700

1.00 0.000E+ 152700

1.00 0.000E+ 106600

1.00 0,000E+ 340

Alpha2U (%)

2.39

0.56

0.67

0.36

0.34

0.37

0.32

0.31

0.31

0.31

0.38

0.38

0.90

0.40

0.36

0.81

0.75

0.66

0.79

4,40

c(t)(cpm)

o

1892

1251

5043

5615

4689

6275

6625

6586

6691

4318

4346

571

3966

4843

622

993

1336

670

130

Ret.Errorc(t)

0.000

0.073

0.110

0,035

0.030

0.030

0.024

0.023

0.023

0.023

0,034

0.033

0.242

0.041

0.031

0.125

0.110

0.084

0.125

0.631

A(t)

o

1892

1251

5043

5615

4689

6275

6625

6586

6691

4318

4348

571

3966

4843

822

993

1336

870

130

Rel.ErrorA(t)

0.015

0.074

0.111

0.038

0.034

0,033

0.028

0.027

0.028

0027

0.037

0.036

0.243

0.044

0.034

0.126

0.111

0.085

0.126

0.631

NR

1.000

0.756

0.839

0.350

0.277

0.396

0.192

0.147

0.152

0.136

0.444

0.440

0.926

0.489

0.376

0.694

0.872

0.826

0.688

0.963

Rel,ErrorNR

0+000

0.029

0,023

0.113

0.153

0.089

0.235

0.323

0.311

0.345

0.076

0.077

0.020

0.068

0.098

0.016

0.018

0.020

0.017

0.014

EtchRate(Vm/min)

2.94E-01

8.OIE-01

8.89E-01

1.61E-01

1.27E-01

1.16E-01

8.82E-02

6.74E-02

1.61E-01

1.47E-Of

9.57E-02

9.49E-02

2.00E-01

1.06E-01

8.’12E-O2

1.07E-01

1.05E-01

t ,79E-01

1.92E-01

1.18E.01

146

Page 165: LosAlamos - International Atomic Energy Agency

ID(IJin)

288 203

289 203

290 203

291 209

292 209

293 204

294 204

295 53

296 53

297 293

298 293

301 145

302 145

303 248

304 248

307 248

308 248

309 248

310 248

Rel. Absorb Transmitted Press.error, t Power

0.010

0.010

0.010

0.009

0.009

0.009

0.009

0.033

0.033

0.007

0.007

0.013

0.013

0.008

0.008

0.008

0.008

0.008

0.008

(w)

49.6

101.9

101.9

50.6

50.6

23.5

23.5

98.2

98.2

50.3

50.3

50.5

50.5

49.6

49.8

50.4

50.4

23,5

23.5

Power(w)

120

240

240

120

120

72

72

240

240

120

120

120

120

120

120

120

120

72

72

(Pa)

17.5

17.5

17.5

10.9

10.9

17.3

17.3

40.3

40.3

34.9

34.9

34.9

34.9

17.3

17.3

35.2

35.2

17.3

17.3

Table C-1. Depleted U02 Experimental Data

NF3Flow(cm)

51

40

48

31

31

52

52

101

101

101

101

104

io4

51

51

102

102

52

52

Sheath(w

-135

-240

-240

-186

-186

-85

-85

-113

-113

-20

-20

-20

-20

-135

-135

-19

-19

-82

-82

Dilution Rel. Alpha AlphaFactor Error Detector 20 (Y.)

1.00

1.00

1.00

1.00

1.00

1.00

1,00

1.00

1.00

1,00

1.00

1.00

t .00

1.00

1.00

1.00

1,00

1.00

1.00

dilution

000.000E+

000.000E+

000.000E+

000.000E+

000.000E+

O.O::E+00

0.000E+00

0.000E+

O.O::E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

147

(c.)(cpm)

722

168

218

2725

2755

4174

4053

469

314

250

249

1074

775

775

535

525

778

3675

.,

0.96

1.99

f.75

0.49

0.49

0.40

0.41

1.19

1.46

163

1.64

0.79

0.93

0.93

1.12

1.13

0.93

0.43

0.43

c(t) Rel. A(t) Rel. NR Ret,(cpm) Error (dpm) Error Error

c(t) A(t) NR

520

0

2

2543

2572

4014

3887

256

97

0.209 520

0.001 0

72.830 2

0.048 2543

0.048 2572

0.032 4014

0.033 3887

0.436 256

1.156 97

0.209

0.015

72.830

0.050

0.050

0.035

0.037

0.436

1.156

0.933

1.000

1,000

0.672

0.669

0.483

0.499

0.967

0.988

0.015

0,001

0.014

0.034

0.034

0.064

0.081

0.015

0,015

Etch Rate(pmlmin)

1.12E-01

1.20E-01

1:20E-01

7,84E-02

7.80E-02

5.77E-02

5.97E-02

4.45E-01

-4k4E-ol

o 0.000 0 0.015 1.000 0!000 8.32E-02

o 0.000 0 0015 1.000 0.000 8.32E-02

815 0.172 815 0.173 0.895 0.021 1.50E-01

520 0.260 520 0.260 0.933 0.019 1.57E-01

568 0.196 568 0.197 0.927 0.016 9.11 E-02

317 0.381 317 0.361 0.959 0.018 9.43E-02

309 0.368 309 0.368 0.960 0.015 9.44E-02

559 0.210 559 0.211 0.928 0.017 9.12E-02

3493 0.037 3493 0.040 0.550 0.051 5.41E-02

3497 0.037 3497 0.040 0.550 0,051 5.40E-02

Page 166: LosAlamos - International Atomic Energy Agency

Table C-1. Depleted U02 Experimental Data

ID

311

312

313

314

315

316

317

318

319

320

321

322

323

324

327

328

329

330

331

332

(din)

23

23

158

158

158

158

23

23

303

303

203

203

8

8

83

83

23

23

53

53

Rel. Absorb Transmitted Presserror, t Power

w)

0.067 49.7

0,067 49.7

0.012 49.6

0.012 49.6

0,012 23.6

0.012 23.6

0.067 169.5

0.067 169.5

0.006 23.6

0,006 23.6

0.010 96.1

0.010 96.1

0.133 167.5

0.133 167.5

0.022 148.8

0.022 148.8

0.067 150.0

0.067 150.0

0.033 167.5

0.033 167.5

Power

w)

120

120

120

120

72

72

400

400

72

72

240

240

400

400

400

400

400

400

400

400

(Pa)

30.9

30.9

17.1

17,1

16.9

16,9

17.2

17.2

17.2

17.2

10.8

10.8

17.1

17,1

10.5

10.5

10.4

10.4

17,3

17.3

NF3Flow(cm)

68

88

50

50

51

51

54

54

51

51

30

30

51

51

31

31

32

32

51

51

Sheath(v)

-70

-70

-133

-133

-77

-77

-340

-340

-89

-89

-268

.268

-334

-334

-378

-378

-375

-375

-340

-340

Dilution Rel. Alpha Alpha c(t) Rel, A(t) Rel. NR Ret. EtchRateFactor Error Detector20(%) (cPm) Error (dpm) Error Error (pm/mIn)

1.00

1.00

1.00

1.00

1.00

1,00

1.00

1.00

1.00

1.00

1,00

1.00

1,00

1,00

1.00

1,00

1.00

1.00

1.00

1.00

dilution

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+00

0,000E+00

0.000E+00

0.000E+00

0.000E+00

0,000E+00

0.000E+00

0.000E+00

0.000E+00

0.000E+

O.O::E+00

0.000E+00

0.000E+00

0.000E+

O.O::E+

148

(c.)(cc&)

4679

667

540

3608

3849

1290

1919

4254

3732

163

334

4155

4580

741

923

4107

4198

539

531

c(t)

0.35 5243 0.027

0.38 4493 0.033

1.00 439 0.277

1.11 301 0.415

0.43 3422 0.039

0.42 3663 0.037

0.72 1070 0.115

0.59 1721 0.070

0.40 4077 0.034

0.42 3539 0.039

2.02 0 0.000

1,41 78 1.693

0.40 3961 0.037

0.38 4390 0.034

0.95 478 0.291

0.85 658 0.216

0.40 3912 0.037

0<40 40!3 0.035

1.11 282 0.474

1.12 270 0.503

5243

4493

439

301

3422

3863

1070

1721

4077

3539

0

78

3961

4390

478

658

3912

4013

282

270

A(t) NR

0.031 0.325 0.119

0,036 0.421 0.083

0.277 0.944 0.017

0.416 0.961 0.017

0.042 0.559 0.050

0.040 0.528 0.056

0.116 0.862 0.020

0.071 0,778 0.024

0.037 0.475 0.067

0.042 0.544 0.054

0.015 1.000 0.000’

1.693 0990 0.017

0.040 0.490 0.065

0.037 0.435 0.079

0.291 0.938 0,019

0216 0.915 0.021

0.040 0.496 0.063

0,038 0.483 0.066

0.474 0.964 0.018

0.503 0.965 0.018

3.44E-01

4.46E-01

1.46E-01

1.48E-01

8.63E-02

8.15E-02

9<14E-01

8.25E-01

3,82E-02

4.38E42

1,20E-01

I,19E-01

1.49E+O0

1.32E+O0

2.76E-01

2,69E-01

5.26E-01

5.12E-01

4.43E-01

4.44E-01

Page 167: LosAlamos - International Atomic Energy Agency

ID

333

334

335

336

337

336

339

340

341

342

343

344

345

346

(M’in)

8

8

8

8

23

23

83

63

113

113

83

83

113

113

Rel. Absorb Transmitted Press.error, t Power

w)

0.133 179.8

0.133 179.8

0.133 160.0

0.133 180.0

0.087 179.9

0.067 179.9

0.022 96.1

0.022 96.1

0.017 96.1

0.017 96.1

0.022 166,7

0.022 166.7

0.017 148.8

0.017 148.8

Power (Pa)(w)

400

400

400

400

400

400

240

240

240

240

400

400

400

400

35.5

35.5

31.2

31.2

31.1

31.1

10.8

10.8

10.8

10.8

17.1

17.1

10.5

10.5

Table C-1. Depleted UOZ Experimental Data

NF3Flow(cm)

92

92

82

82

81

81

30

30

30

30

50

50

31

31

Sheath(v)

-255

-255

-272

-272

-272

-272

-280

-280

-277

-277

-347

-347

-385

-385

Dilution Rel, Alpha Alpha c(t) Rel.Factor Error Detector 20 (%) (cpm) Error

dilution (c.) c(t)(cpm)

001.00 0.000E+ 648 1.01 416 0.295

001.00 0.000E+ 986 0.62 782 0.143

001.00 0.000E+ 1144 0.76 925 0.131

001.00 0,000E+ 1757 0.62 1550 0.079

001.00 0.000E+ 247 1.64 17 6.813

001.00 0.000E+ 424 1.25 188 0.651

001.00 0.000E+ 1101 0.78 916 0.114

001,00 0,000E+ 1878 0.60 1664 0,070

001.00 0.000E+ 1204 0.74 973 0,132

001.00 0,000E+ 834 0.89 604 0.204

001.00 0.000E+ 406 1.28 154 0.849

001,00 0.000E+ 670 1.00 415 0.324

001.00 0.000E+ 1006,22 0,814 753 0.162

001.00 0.000E+ 1207.11 0.7432 962 0.141

A(t)

416

782

925

1550

17

168

916

1684

973

604

154

415

753

962

Rel. NR Ret. Etch RateError Error Qunlmin)A(t) NR

0.298 0.946

0.144 0.899

0.132 0.881

0,080 0.800

8.813 0.996

0.651 0.976

0.115 0.882

0.071 0.783

0.133 0.875

0.205 0.922

0.650 0.980

0.017

0.017

0.019

0,023

0.015

0.016

0.017

0.024

0.020

0.018

0.017

2.86E+O0

2.74E+O0

2.68E+O0

2.44E+O0

1.06E+O0

1.03E+O0

2.59E-01

2.30E-01

1.89E-01

1.99E-01

2.88E-01

(.324 0.947 0.019 2.78E-01

0.182 0.903 0.020 1.95E-01

0.142 0.876 0.021 1,89E-0100

149

..-—

Page 168: LosAlamos - International Atomic Energy Agency

APPENDIX D. CHEMKIN

This appendix includes details of the Chemkin validation not

the main text.

D.1. Thermodynamic Data

The following thermodynamic data includes all CHEMKIN gas

required to run CHEMKIN, and is

code, which is a polynomial fit for

constant pressure as a function of

with the FITDAT utility. The data

based on the NASA Chemical

the enthalpy, entropy, and spe

temperature. These fits may b{

shown below are the coetlicier

equations, and details are available in the CHEMKIN Ill (Kee et. al.

SURFACE CHEMKIN Ill (Coltrin et. al, 1996) documentation.

D. 1.1. Thermodynamic Data for CHEMtUN Ill:THERMO

300.000 1000.000 5000.000E 120186E 1 G 0300.00 5000.00 1000.000.02500000E+02 O.OOOOOOOOE+OO 0.0000OOOOE+OO 0.0000OOOOE+OO O.OOOOOOOOE+OO

-0.07453749E+04-0.01173403 E+03 0.02500000E+02 O.OOOOOOOOE+OO 0.0000OOOOF,+OO0.0000OOOOE+OO 0.00000000E+00-0.07453750E+04-0.01173403E+03

F 121286F 1 G 0300.00 5000.00 1000.00O.O2687459E+O2-O.O2O1O358E-O2 0.08597957E-06-0.01644974E-09 0.01166160E-130.08722883E+05 0.03882212E+02 0.02913905E+02-0.07336339E-02 O.O5571O15E-O5

-0.02666871E-OB 0.08643255E-12 0.08651201E+05 0.02677115E+02F2 121286F 2 G 0300.00 5000.00 1000.000.04018308E+02 0.06221479E-02-0.02420845E-05 0.04742076E-09-O.03418141E-13

-0.01300713E+05 0.01126327E+02 0.02940287E+02 0.03491492E-01-O-02458208E-040.01837073E-08 O.O285O917E-1I-O.O1O1O43OE+O5 0.06694194E+02

N2F2 42489F 2N 2 G 0300.00 3000.00 1000.000.07255211E+02 O.O227441OE-O1-O.O2793346E-O5-O.02203844E-08 0.05359234E-120.06360353E+C5-0 .O1O94248E+O3 0.03127143E+02 O.O1O57134E+OO-O.O9746112E-O5

-0.07208357E-07 O.O3567978E-10 0.07615831E+05 O.O11O7465E+O3N 12018614 1 G 0300.00 5000.00 1000.000.02450268E+02 O.O1O66146E-O2-O.O7465337E-O6 O.O1879652E-O9-O.O1O25984E-130.05611604E+06 0.04448758E+02 0.02503071E+02-O.02180018E-03 0.05420529S-06

-0.05647560E-09 0.02099904E-12 0.05609890E+06 0.04167566E+02N2 121286N 2 G 0300.00 5000.00 1000.000.02926640E+02 0.01487977E-01-O.05684761E-05 O.O1OO97O4E-O8-O.O6753351E-13

-0.09227977E+04 0.05980528E+02 0.03298677E+02 0.01408240E-01-O.03963222E-04O.O5641515E-C7-O.O2444855E-1O-O.O1O2O9OOE+O5 0.03950372E+02

N3 121286N 3 G 0300.00 5000.00 1000.000.05208505E+G2 O.O24445O7E-O1-O.O1O38941E-O4 0.019774:7E-08-O.01395644E-120.04796i78E+06-O.03612756E+02 0.02882219E+02 0.08930338E-01-O.08539038E-04O.O5O45585E-O7-O.OI521248E-1O 0.04863468E+06 0.08481757E+02

NF 121286N lF 1 G 0300.OG 5000.00 1000.000.03862177E+02 0.07551806E-02-O.03044943E-05 0.05874447E-09-O.04187479E-130.02867243E+06 0.03457233E+02 0.02871947E+02 0.03312153E-Oi-O.02691159E-040.01121951E-O?-C.02475131E-11 C.02896257E+06 0.08640247E+02

NF3 62394N lF 3 0 OG 300.000 4000.000 1000.000.82191658E+01 0.12927436E-02-O.16520647E-06-O.68563703E-10 0.14209565E-13

-0.17080596E+G5-C.17275919E+02 0.29812291E+01 O.116O531OE-O1-O.974O7462E-O6-0.84367731E-08 0.41166593E-11-O.15457758E+05 O.1O762127E+O2NF2 62394N lF 2 0 OG 300.000 4000.000 1000.000.59553924.E+O1 O.75965584E–O3-O.1O16646OE-O6-O.3781O439E-1O 0.80034466E-140.18727911E+04-O.49131246E+01 0.31983922E+01 0.59982142E-02-O.45932120E-06

-O.4O1O1686E-O8 0.18564607E-11 0.27531292E+04 0.99338350E+01

150

Page 169: LosAlamos - International Atomic Energy Agency

N2F4 L12/86N 2F 4 0 OG 298.150 5000.000 1000.001.29150660E+01 3.50813620E-03-1.55468900E-06 3.O456218OE-10-2.1952354OE-14

-7.2OO8189OE+O3-3.771O8998E+O1 9.87812940E-01 5.00295240E-02-7.36767080E-055.2523455OE-O8-1.4712961OE-11-4 .6101O86OE+O3 2.04857192E+01-2.64600820E+03

F+ J 6182F lE -1 0 OG 298.150 6000.000 1000.002.68834861E+O0-1.76182961E-04 6.06940639E-08-8.91530067E-12 5.47552167E-162.11744095E+05 4.27480838E+O0 3.O8421O84E+OO-9.OOO62139E-O4-1.64599174E-O?1.10121336E-O9-5.5627O92OE-I3 2.11619101E+O5 2.14597653E+O0 2.12499113E+05

F- J 6/82F lE 1 0 OG 298.150 6000.000 1000.002.50000000E+O0 0.0000OOOOE+OO 0.0000OOOOE+OO 0.0000OOOOE+OO 0.0000OOOOE+OO-3.14241522E+04 3.26488285E+O0 2.50000000E+O0 0.0000OOOOE+OO 0.0000OOOOE+OO0.0000OOOOE+OO 0.0000OOOOE+OO-3-14241522E+04 3.26488285E+OO-3.06787772E+04

N+ L 7/88N lZ -1 0 OG 298.150 6000.000 1000.002.51112967E+O0 3.46441751E-06-1.59426938E-08 7.24865663E-12-6.44501426E-162.25624340E+05 4.92767661E+O0 2.80269445E+O0-1.44758911E-03 2.77118380E-06

-2.40187352E-09 7.80839931E-13 2.25575244E+05 3.57877835E+O0 2.26366632E+05N- L 7/88N lE 1 0 OG 298.150 6000.000 1000.002.50897099E+O0-9.58412751E-06 3.8521OO62E-O9-5.68935998E-13 4.20991172E-175.62083017E+04 4.94953202E+O0 2.62723403E+OO-5.93445018E-04 1.12028916E-06

-9.62585603E-1O 3.11119557E-13 5.61880871E+04 4.40111176E+O0 5.69531625E+04N2+ TPIS89N 2E -1 0 OG 298.150 6000.000 1000.003.58661363E+O0 2.53071949E-04 1.84778214E-07-4.55257223E-11 3.26818029E-151.80390994E+05 3.09584150E+O0 3.77540711E+00-2 .06459157E-03 4.75752301E-06

-3.15664228E-09 6.70509973E-13 1.80481115E+05 2.69322186E+O0 1.8I551099E+O5N2- J 9/77N 2E 1 0 OG 298.150 5000.000 1000.003.11567530E+O0 1.45886880E-03-6.01731480E-07 1.I348423OE-10-7.9658518OE-151.68590580E+04 6.38985600E+O0 3.88268480E+OO-3.19244460E-03 8.52278380E-06

-7.34037460E-09 2.20568150E-12 1.67969350E+04 3.11180520E+O0 1.?8744680E+04Z2+ 90994N OF 2E -1 OG 300.000 4000.000 1400.000.40871696E+01 0.28773994E-03-O.42124171E-07-O. 10744347E-10 0.24084770E-140.38982081E+06 0.19017669E+01 0.30832281E+01 0.20225300E-02-O.37376336E-06

-0.72879480E-09 0.31362716E-12 0.39018441E+06 0.74287305E+01NF3+ 90994N lF’ 3E -1 OG 300.000 4000.000 1400-000.82772875E+01 0.12120609E-02-0. 14293019E-06-O.65834289E-10 0.13135263E-130.28434403E+06-0.17602449E+02 0.35353677E+01 O.1OO82626E-O1-O.19761912E-O5

-0.41118668E-08 0.18401435E-11 0.28588697E+06 0.80730133E+01NF2+ 90994N lF 2E -1 OG 300.000 4000.000 1400.000.60226760E+01 0.68474363.E-03-0.858O5958E-O7-O.34O53354E-1O 0.69562801E-140.27545450E+06-0.53112230E+01 0.34224713E+01 O-54404330E-02-O.i0449339E-05

-0.21526023E-08 0.95328823.E-12 0.27632822E+06 0.88361416E+01NF+ 41895N lF lE -1 G 0300.00 5000.00 1000.000.03862177E+02 0.07551806E-02-O.03044943E-05 0.05874447E-09-O.04187479E-131.69734638E+05 0.03457233E+02 0.02871947E+02 0.03312193E.-O1-O.O2691159E-O40.01121951E-07-O.02475131E-11 1.70024780E+05 0.08640247E+02

END

D.1.2. Thermodynamic DataforSURFACE CHEMKINIII:

MATERIAL CHM4BERSITE/WALL/ SDEN/4.05E-9/ !SDEN based on Al 2.702 g/cm3, 4.04A crystal,AL(S) ALF(S) ALF2(S) ALF3(S)END

1234123412341234123412341234

01234

91234

012341234

26.9815g/mol

SITE/SILICON/ SDEN/5.63E-10/ !SDEN based on Si crystal, 5.43A, cubic SDEN= l/a”2*NaS1(S) SIF(S) SIF2 {s) SIF3(S)END

BULK SI(B) /2.33/THZFU40300 500 1000AL(S) 62987AL 1 G 0300.00 5000.00 0600.00O.O2559589E+O2-O.1O632239E-O3 O.O72O2828E-O6-O.O212I1O5E-O9 0.02289429E-130.03890214E+06 0.05234522E+02 0.02736825E+02-0 .05512374E-02-O.04033937E-050.02322343E-07-O.01705599E-iO 0.03886794E+06 0.04363879E+02! Thermodynamic values for ALF, ALF2, ALF3 need to be redone.ALF(S) 32989AL IF 1 G 0300.00 4000.00 1000.000.02775845E+02-0.06213257E-02 0.04843696E-05-O.12756146E-09 0.i1344813E-130.05339790E+06 0.04543298E+02 0.03113515E+02-O.02330991E-01 0.03518530E-04

-0.02417573E-07 0.06391902E-11 0.05335061E+06 0.03009718E+02ALF2 (S) 32989AL iF 2 G 0300.00 4000.00 1000.000.02775845E+02-O.06213257E-02 0.04843696E-05-O.12756146E-09 0.11344818E-130.05339790E+06 0.04543298E+02 0.03113515E+02-O.02330991E-01 0.03518530E-04

-0.02417573E-07 0.06391902E-ii 0.05335061E+06 0.03C09718E+02ALF3 (s) 32989AL lF 3 G 0300.00 4000.OC 1000.000.02775845E+02-O.06213257E-02 0.04843696E-05-O.12756146E-09 0.i1344818E-i30.05339790E+06 0.04543298Z+C2 0.03113515E+02-O.02330991E-01 0.03518530E-04

151

1234

12341234123

Page 170: LosAlamos - International Atomic Energy Agency

-0.02417573E-07 0.06391902E-11 0.05335061E+06 0.03009718E+02 4S1(S) J 3/67S1 100 0000 0000 00G 300.000 5000.000 1

0.26506014F, 01-O.35763852E-03 O.29592293E-O6-O.728O4829E-1O o.57963329E-14 20.53437054E 05 0.52204057E 01 0.31793537E 01-O.27646992E-02 0.44784038E-05 3

-0.32833177E-08 0.91213631E-12 0.53339032E 05 0.27273204E 01SIF(S)

0.00000000 441S89S1 lF 1 0 OG 300.000 3000.000 1000.00 0 1

0.41200666)2+010.35488207E-03-0.72002223E-07-0.21904345E-10 0.67645906E-14 2-0.75613784E+04 0.27842460E+01 0.31449478E+01 0.2S885573E-02-O.57959124E-06 3-0.18072788E-08 O.1O411718E-11-O.7294439OE+O4 0.78767738E+01 4SIF2 (S) 41889S1 lF 2 0 OG 300.000 3000-000 1000.00 0 10.61424704E+01 0.78079745E-03-O.13393120E-06-O.62648393E-10 0.17251383E-13 2

-0.77440422E+05-O.47123275E+01 0.38453453E+01 0.60384651E-02-O.11677322E-05 3-0.45795536E-08 0.26074143E-11-O.76816336E+05 0.72729836E+01SIF3(S) 41889S1 lF 3 0 OG 300.000 3000.000 1000.00 0 :0.85247898E+OI O.13237924E-O2-O.21O42787E-O6-O.11495040E-09 0.30553014E-13 2

-0.12235223E+06-O.15502343E+02 0.46628685E+01 O.1OO87878E-O1-O.18O55442E-O5 3-0.77692990E-08 0.43778518E-11-O.12129652E+06 0.46729660E+01 4S1 (B) J 3/67S1 100 000 000 OS 300.000 1685.000 1O.24753989E 01 0.88112187E-03-O.20939481E-06 0.42757187E-11 0.16006564E-13 2

-0.81255620E 03-O.12188747E 02 0.84197538E 00 O.8371O416E-O2-O.13O77O3OE-O4 30.97593603E-08-O.27279380E-11-O.52486288E 03-O.45272678’E01 4

END

D.2. Pressure and Mole Fraction Estimates in Perrin et. al. (1990)Experiment

At RF power other than 200 W, the total system pressure in the

experimental setup of Perrin et.al., 1990 cannot redetermined. Butthepar&ial

pressures ofall species except HF are known at all pressures, and thus theHF

pressure can reestimated bya ratio method as shown in Figure D-1. The

results for total pressure and the experimental mole fractions obtained from

Perrin’sfigure8 are shown in Table D-1.

Comparison of Chemkin with these experimental valuesare shown in

Figure D-2. At200 W, Chemkin and experiment compare to within ~ 5.3 ‘A

relative error. The error increases at lower power with CHEMKIN predicting

lower NF~dissociation than experiment, less SiFd formed, and less N2 formed.

Although the relative error becomes large, the overall comparison is reasonable,

given the complexity ofthe reactions.

Table D-l. Experimental Mole Fractions&Pressure

Power (W) 300 200 150 100 50NF3 0.144 0.253 0.329 0.466 0.664N2 0.353 0.315 0.294 0.24 0.154SiFg 0.455 0.408 0.37 0.308 0.199Other (N2F4, HF) 0.292 0.224 0.’t8O 0.121 0.062TOTAL 1.244 1.200 1.173 1.135 1.079Pressure (Pa) 12.4 12.0 11.7 11.3 10.8

152

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A summaty of all the CHEMKIN predicted species mole fractions, )$, from

Pernn et. al. (1990) experiment from 50 to 300 W is included in Table D-2.

12.5 r 1 I J 1

12.0

11.5

11.0

10.51~1y=8. 12e-8x3-5.92e-5x2+cx+10 max dev2.48E-8,?=1.00C=O.0186

urve with knownpj forced at 200W

by allowing linear termo

orIly to varyO pj Of NF3, N2i SiF4, and N2F4

\y=ax3+bx2+cx+lOmaxdevO.0896,r2=0.990a=8.12E-8,b=-5.92E-5,c=O.0168

,00 ~

o 100 200 300

RF Power (W)

Figure D-1. Determining the HF Partial Pressure

0.8

0.6

0.4

0.2

1 1 1

\

+Solid-Experimental

Q\Dashed–CHEMKl N

7

l\\\\

o~ I i I I

100 200 300

Power (W)

Figure D-2. Comparison of Chemkin and Experiment

153

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Table D-2. CHEMKIN Predictions, ~, for Perrin’s Experiment

Power (W)300 200 150” 100 50

Electrons 9.03E-06 1.88E-06 8.32E-07 3.21 E-O? 7.89E-08N 12.38E-02 4.04E-03 1.75E-03 7.15E-04 1.93E-04N2 “0.288 0.248 0.204 0.140 1 0.058Ns 2.06E-26 3.49E-26 3.44E-26 2.79E-26 1.52E-26N+ 1.60E-06 3.35E-08 4.69E-09 5.91E-10 4.09E-11N2+ 4.17E-06 9.09E-07 3.17E-07 8.56E-08 1.15E-08

fNFa 0.079 0.218 0.342 0.521 0.760

NF* 2.43E-03 9.OIE-03 1.41 E-02 1.93E-02 12.23E-02NF ]2.65E-03 \4.17E-03 4.01 E-03 [3.25E-03 1.95E-03N*F* 11.82E-04 12.83E-03 6.58E-0311 .16E-02 1.44E-02

NZF4 13.64E-11 4.92E-10 1.17E-09 12.14E-09 2.71 E-09

F2 0.003 0.019 0.021 0.015 0.006F i 0.202 0.162 I 0.129 I 0.089 / o.04flF+ 1.79E-07 6.84E-08 3.16E-08~1.llE-08 2.08E-09F2+ 2.47E-08 3.36E-08 1.57E-08 4.42E-09 5.34E-10NF+ 2.98E-06 1.56E-06 1.24E-06 1.06E-06 9.03E-07NF2+ 3. 19E-05 4.67E-05 4.82E-05 4.38E-05 3.03E-05NF3+ 1. 17E-04 7.12E-05 4.79E-05 2.75E-05 1.12E-05

F- 1.49E-04 1.1 9E-04 19.69E-05 7.22E-05 4.23E-05

S}Fq 0.399 0.333 0.277 0.199 0.096

0.3. Predictions of Mole Fractions for U02 Etching Experiment

Mole fraction predictions forthe UOzetching expefimentat 17 are shown

below. The parameters set in CHEMKIN are summarized in Table D-3. The NFs

flow rate varied from 5.34 to 5.71 SCCM. The conditions for a well mixed reactor

applies best at 17 Pa since the glow fills the entire chamber.

Table D-3. CHEMKIN Parameters for U02 Etching Experiment

item Value

Volume {ms) 0.125Area (m2j 1.604Power (W) 25 to 250Pressure, piasma (Pa) 17Flow (SCCM) 5.34 to 5.71Ambient Temperature (K) 298H (W m-2 s-’) 1486

154

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Predicted species mole fractions at 17 Pa are tabulated in Table D-4 as a function of power absorbed in the

plasma.

Table D-4. CHEMKIN Predicted Mole Fractions at 17 Pa for UOZ Etching Experiments.

Power(W)Species 25 50 75 100 125 150 175 200 225 250E 4.77E-10 1.75E-09 3.76E-09 6.66E-09 1.06E-08 1.57E-08 2.24E-08 3.09E-08 4.19E-08 5.66E-08N 1.57E-07 3.30E-07 5.44E-07 8.16E-07 1.16E-06 1.57E-06 2.06E-06 2.64E-06 3.34E-06 4.21 E-06N2 1.22E-02 2.74E-02 4.25E-02 5.62E-02 6.77E-02 7.74E-02 8.56E-02 9.30E-02 9.97E-02 1.06E-01N3 3.63E-57 5.20E-57 6.18E-57 7. IOE-57 8.19E-57 9.52E-57 1.11 E-56 1.30E-56 1.52E-56 I’.78E-56N+ 1.44E-16 7.94E-16 2.61E-15 7.OIE-15 1.66E-14 3.59E-14 7.27E-14 1.42E-13 2.73E-13 5,30E-13N2+ 1.07 E-I 1 5.71 E-11 1.66E-10 3.74E-10 7.22E-10 1.26E-09 2.06E-09 3.26E-09 5.06E-09 7.86E-09NF3 0.89993 0.7994 6.99E-01 6.05E-01 5.24E-01 4.55E-01 3.94E-01 3.40E-01 2.90E-01 2,44E-01NF2 8.91 E-03 1.03E-02 1.09E-02 1.14E-02 1.19E-02 1.24E-02 1.28E-02 1.32E-02 1.34E-02 1.35E-02NF 1.87E-12 2.33E-12 2.65E-12 2.99E-12 3.42E-12 3.94E-12 4.56E-12 5.28E-12 6. IOE-12 7,04E-12N2F2 3.13E-09 1.58E-09 9.84E-10 7.OIE-10 5.55E-10 4.70E-10 4.14E-10 3.72E-10 3.36E-10 3.OIE-10NzF4 4.48E-04 2. 15E-04 1.25E-04 8.25E-05 5.96E-05 4.56E-05 3.60E-05 2.87E-05 2.28E-05 1.78E-05F2 4.57E-03 1.24E-02 1.85E-02 2.17E-02 2.22E-02 2.12E-02 1.94E-02 1.73E-02 1.51 E-02 1.29E-02F 7.39E-02 0.15032 2.29E-01 3.05E-01 3.74E-01 4.34E-01 4.88E-01 5.36E-01 5.81 E-01 6.24E-01F+ 1,72 E-1 1 7.49 E-I 1 1.96E-10 4.11 E-10 7.44E-10 1.22E-09 1.88E-09 2.76E-09 3.94E-09 5.55E-09F2+ 1.89E-12 1.23 E-I 1 3.52 E-I 1 7.21 E-I 1 1.22E-10 1.82E-10 2.53E-10 3.37E-10 4.38E-10 5.62E-10NF+ 1.49E-08 1.75E-08 1.97E-08 2.11 E-08 2.16E-08 2.15E-08 2.09E-08 2.01 E-08 1.89E-08 1.75E-08NF2+ 2.70E-06 4.62E-06 6.05E-06 7.15E-06 8.00E-06 8.64E-06 9.11 E-06 9.40E-06 9.54E-06 9.51E-06NF3+ 8.74E-07 1.92E-06 3.02E-06 4.19E-06 5.41 E-06 6.66E-06 7.94E-06 9.24E-06 1.06E-05 1.20E-05F- 3.59E-06 6.55E-06 9.09E-06 1.14E-05 1.34E-05 1.53E-05 1.70E-05 1.86E-05 2.01 E-05 2,15E-05

155

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D.4. Reveree Rate Coefficient Calculation

The reverse rate coefficient, k,, can be obtained from Gibbs free energy of

formation of the species in a given reaction and the forward rate constant, kf

(Alberty and Silbey, 1997). The forward rate constant, kf is given by equation

(D-1 ). C/R””has units of K; R is the gas constant, B is dimensionless, T is the

temperature (K), v, is the stoichiometric coefficient of the reaction (positive for

products, negative for reactants), j is the species type, and k. is the rate

rconstants with units of (cm3nzolecule ‘]S-l, where n is the order of reaction,

Equations (D-2) through(D-5) show the development needed to obtain the

reverse rate coefficient from the equilibrium rate coefficient for a reaction. Co

and PO are the concentration and pressure of an ideal gas in the standard state

(1 mol/L, 1 bar). Although Gf values are pressure and temperature dependent,

the corrections are less than 0.075 kJ/mole (Appendix E) and can be neglected

for the operating conditions of the plasma.

kf = kOT8e-& (D-1 )

G, =~vjGy {D-2)

Gr = hThKP (D-3)

-x”,Kc = (CORT/ p“) ‘ Kp (D-4)

(D-5)

D.5. Sticking Coefficient

The sticking coefficient, y, a dimensionless quantity defined as the

reaction rate divided by the incoming flux of species, is the probability of a

surface reaction. Conversion from sticking coefficient to rate constant is

accomplished as described in the CHEMKIN documentation (Coltrin et. al., 1996)

and summarized by Equation (D-6). In this equation, R is the gas constant, T the

temperature, M the molecular weight, r the surface site concentration, and VI the

156

Page 175: LosAlamos - International Atomic Energy Agency

stoichiometric coefficient (positive for products

surface site concentration may be calculated

(assumed cubic) and Avogadro’s number.

1?57

and negative for reactants). The

from the crystal dimensions, a,

(D-6)

(D-7)

Page 176: LosAlamos - International Atomic Energy Agency

APPENDIX

El. Etch Rate Conversion

E. ANALYSIS

The etch rate of the UOZ, J(t), is obtained from the following relationships

with ~R a dimensionless variable representing” the fraction of UC)2activity etched

from the stainless steel planchette, t the plasma immersion time, and r the

characteristic etch time.

NR = N,,= (1 -e- ‘i’). (E-1)

[1dN~ N~,=J(t) = — e< = JOe<.

dt=r(E-2)

To convert J from inverse minutes to micrometers per minute, the

relationships shown below are applied. in these expressions, ~R are the moies

of UOP etched, mR is the mass of U02 etched, M is the molecular weight of U02,

N are the number of molecules etched, NA is Avogadro’s number, f is the activity

ratio of 2%U, tln is the half-life of 238U,AO is the initial activity of the sample, A is

the final activity of the sample, S is the surface area of the sample, p is the

density of the UQ2 sample, NR is given by equation (E-1), and J is given by

equation (E-2). The error in assuming that the number .of molecules, N, is equal

to the number of 238Umolecules is less than 0.05Y0. The assumptions inherent

in this derivation are that the sample is uniform, that etching is along the axis of

the cylindrical stainless steel planchette, and the surface area, S, remains

constant.

(E-3)

(E-4)

dqR = 1 dm~ _ Sp dh fll,zAo dN~.— _—— (E-5)dt M dt M dt = N. in(2) dt ‘

$=E?2LI-’”)158

(E-6)

Page 177: LosAlamos - International Atomic Energy Agency

Ave($) =[1Mt112fAo NR (E-7)@NA in(2) Y

dm [1~=/+=:;:, J(t). (E-8)

A

Table E-1 contains the parameters needed in the calculation of the el

rate, equations (E-6) and (E-8). The value in brackets in Equation (E-7) is 27.

pm and in equation (E-8) it’s 10.56 mg. The mass etch rate is better express

as a mass flux in which case the factor in equation (E-8) normalized to the crc

sectional area of the sample, S, becomes 13.3 mg/cm2.

Table E-1. Parameters for Etch Rate Calculation

Symbol Description VaiueM UOZ Molecular Weight (g/mole) 270.05f Activity Ratio, 238Uto U - 0.895tl/2 Half-life, 238U(years) 4.47X109

Ao Initial Activity of Sample (Bq) 129.4Density of UOZ Sample (g/cm3) 4.8

: Surface area of U02 Sample (cm2) 0.796

E.2. Ion-Molecular Collision Cross Section

The ion-neutral collision cross sections (Lieberman

p. 78) of a number of elements are known, but the cross

NF3 were not found in the literature. By comparing the

cross

cross

cross

cross

& Lichtenberg, 19$

sections for NFz a

geometrical and tr

sections, it was desired to determine if the ion-molecular coliision (tn

sections of NF, NlF2 and NF3 could be estimated from the geometri

sections and the cross sections of the known atoms. The geometri~

section was determined based on the radius of the appropriate elemel

(Aiberty and Siibey, 1997, p. 364).

The NF molecuiar dimensions are given in Lide (1993), and the fiuori

and nitrogen diameters by Aiberty and Siibey (1997), and shown in Figure E

The geometrical cross section of the two moiecules, NF2 and NF3, w{

159

Page 178: LosAlamos - International Atomic Energy Agency

determined based on the NF dimensions and bond angles, using a drawing

program.

A compilation of physical data for species of interest are shown in Table

E-2 and the cross sections are piotted in Figure E-2. The estimated (Est.) true

cross sections in Tabie E-2 are based on the comeiation shown in Figure E-2 for

the true cross section. Based on these resuits, calculations of the cross section

for NF2 or NF3 based on the Ar moiecuie differ by a factor of 1.5 and 2.7,

respectively.

Atomic & Molecular Dimensions/

\

N-F: 135.28pmAngle F-N-F: 103,18dF = 79.2 pmdN = 104,2 pm

F292.82

N~b F

~135.30~

NF2 uF NF3

Figure E-1. NFz and NFs Geometrical Cross Sections

Tabie E-2. Physicai Data on Seiect Species

Species Z M 2radius (m) ~geo (cm ) ~t~e (cm2) O,we

o geo

He 2 4.0026 2.91 E-11 2.66E-17 2.00E-15 75.18F 9 18.9984 3.96E-11 4.93E-17 Est: 2.46E-15 49.96

Ne 10 20.1797 3.54E-11 3.94E-17 2.55E-15 64.77Ar 18 39.948 6.59E-11 1.36E-16 5.27E-15 38.63

NF2 25 52.0035 1.46E-10 6.73E-16 Est:8.03E-15 11.93NF? 34 74.0019 1.57E-10 7.72E-16 Est: 1.41 E-14 18.25

160

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n,01

ECJ

True Cross Section

10-’4 : Ar

He

v c = +2.88E-18M2 -3.57E-17M1 +2. 10E-15

-17He

10! I I

o 20 40 60

Molecular Weight, M (amu)

Figure E-2. Cross Section Correlation

E.3. Ion Energy in Traversing the Plasma Sheath.

ions traversing the plasma sheath undergo acceleration in traversing the

sheath. If there were no collisions, the total energy gained would equal the

effective RF sheath voltage, in electron volts. But because of collisions between

ions and neutral particles in the sheath, the actual energy gained will be less

than the equivalent DC sheath potential. The purpose of this analysis is to

calculate the energy gained by an ion in traversing the sheath based on plasma

theory (Lieberman and Lichtenberg, 1994).

An ion of mass, m, and molecular weight, M, traversing a sheath with an

effective plasma potential,

temperature in eV given

temperature given by TG

V., in volts, in a plasma with pressure, p, electron

by $, ion density given by Xi, and neutral gas

will experience one or more collisions unless the

pressure is less

the permittivity

than 0.4 Pa (Lieberman & Lichtenberg,

of free space (8.854x10-12 F/m), e

161

1994, p. 350). Let ~ be

the charge on an ion

Page 180: LosAlamos - International Atomic Energy Agency

(1.601 x10-’9 C), and m the ion-atom collision cross-section. The following

equations in Table E-3 apply to this development, where the referenced

paragraphs are to Lieberman and Lichtenberg, 1994.

Table E-3. Plasma Sheath Thickness and Ion Energy.

Noxipni =

RT~

Napn~. —RT~

Relationship Description Reference NumberEquationi

e~q=~

Eiectron Temperature (K)(E-9)

p,=Xip Ion Pressure(E-IO)

(E-1 1)Ion number density

II&o@A= —eni

/li=~nG 0,

Plasma density

Debye Length 2.4.22

Ion mean free path in 3.5.7sheath

Bohm Velocity at 6.2.4plasma/sheath interface

Modified Bohm velocity at 11.2.53plasma/sheath interface

IIe~UB. —

mi

u, =

{r)

Al+7r—

2A,

s=p.,; ] ]

0.5 0.4 sheath thickness~,1.5~0.5

2e , from Child’s Law with0;

r eniu, collisions

AVe Ion net kinetic energyE, = 0.62-

5 after traversing the sheath

t 1.2.54

11.2.57

(E-12)

(E-13)

(E-14)

(E-15)

(E-16)

(E-1?)

(E-1 8)

1Equations numbers are those given in Liebermanand Lichtenberg, 1994.162

Page 181: LosAlamos - International Atomic Energy Agency

,,The CHEMKIN predictions of the ion mole fraction, electron energy, and

neutral gas temperature are summarized in Table E4, along with the

experimentally measured sheath voltage. A MathCad calculation of the

parameters is summarized in Table E-5 at 50 W. For a plasma immersion time

of 30 minutes, with ions impinging the electrode from both sides, the power

deposited is 0.378 W for a total energy deposition of 680 J.

Table E-4. Calculated Mole Fractions of Plasma Species at 17 Pa.

Species 50 VV IoowIon,XI 6.6E-06 1.1 E-05Sheath Voltage (V) -142 -261Electron Energy (eV) 5.21 4.87Neutral Temperature (K) 298.2 298.3Sheath Thickness (cm) 0.13 0.16Ion Energy (eV/molecule) 11.3 17.9Ion Energ y (kJ/mol) 1087 1731

The ion energy is not too sensitive above a cross section of 1xl 0-18m2 for

the NF3 ion as shown in Figure E-3.

t i

-o

j

NF~ Ion

Sheath Voltage”-261 V

o

-\o

\

O\o~o

~o (I I

o 1 2 3

Cross Section x 10-’8 (m2)

Figure E-3. ion Energy Dependence on Cross Section.

163

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Ob..0*V0: ~stimato ttao _?t-rgy of -n NF=* ion tr~rsin~ the pIa*ma sho~h andimp_ Cting ● curface. Inc$udo Collisions in th- shosth +- tho Chitd ~. Obtain theplasm= nhwuth thickness. Obtain the enarey dapasite+d an m Z- diarnater stainlessat-d planch~te at a specifted plasm= processing time. l%e equations specK96d arefound in Liabarrnan & Uctnenberg. 1994.

Input- :=1.dol.lo--a Electron Ch=rgo

k :- I,sl .lCI-=.J.K-l 1301tzman Constant

P :* SO.W -l=s?na XSorbad F’_r

p := 17 .p. Plasm- pmssum

na :.71 .- Molecular -ight of ion50~u):=s.21-v Electron Temperature in eV

x ~ :=6s5.10-6 10n Mole Fraction

-r * :.298 .17-K Gas temperature

=i := 1.41 .lQ-1=.*2 ion collision Cross Section

v ● := 142-V Sheath Voltage

t ~ :.m - PIasma Pr0c9ssing Time

Int errnediate Results-I- e-e* :._

k~i:=x

MA

Fi:=xi”P

~.:= pi”NA. R.T ~

p-NAXxe :--—

R.TO

-- ----

T= =6.O4.1O* K

Xui = 1.17P .10-2S k=

pa= I .113-10-* P-

Xla =2.705-101= L*3

A = 1 .032-10-4 m

. . -- .=-. — ---- . . .

A i = 1 .717.10-+ m

u~ =2.66-103?s

~i.l.pos.los=s

Ui:= F=A2.A~

Results

.:=[,.=..o.[~y=.v~:=~:”~ s =o.124-cltl Sheath Thickness

Ji:=ni-ui 3 i = 5.16.10’” ~ Ian Flux to Surfacean= -s

A i.v ● ..3Ei :=0.62. E= = 1.S06.10-xe J Ion Energy

m

Eev :=? Eev=ll.279V

E -1. := Ei.N * = mol. = 1 .0s7 .105-2mol

Q ,=2.J1.A.~. x Q =0.378 W Heat Generatwdfrom 2 sides of planchette

E_Total := Q.tp E_T o%ed = 679 .87S J Total Enary Deposited

R :=S.3144-Jamal- 1 .K- 1

Vel :=0.125-=

L :=0.0365 .cat

d :=2.*

A ,=7?4=T

A = 2.027 .10-3 ma

Electron Temperature

Mass ion

Pressure ion

Ion number density

Gas number Dansity

Debye L=ngth

---- ---- ---- ---- -—--- ----- .

Jon m-an frsa path

EIohm Velocity

Ion Velocity

E_~ux := ~ E_fiux = 1S6 .334 -~ Energy Flux~a

164

Page 183: LosAlamos - International Atomic Energy Agency

E.4. Energy Deposited From Exothermic Reactions of U02 and F

A Mathcad calculation for the maximum energy deposited as heat from

samples of U02 and F atom radicals is included in Table E-6. The maximum

energy deposited as heat from a sample is 62 J. By comparison, the energy

deposited by ion bombardment is 680 J (Table E-5).

165

Page 184: LosAlamos - International Atomic Energy Agency

Table E-6. Energy From U02 Reactions with

Energy Deposition From Exothermic Reactl

- Objective: Estimate the energy deposited on the SS planch~due to reaction of the UQ and F atoms at 50 W RF Power. Assure-energy is converted to heat. Base the estimate on 100 ~ of uranylsample converted to a uniform layer of LQ. Assume that all the U(

* UFe within 30 minutes (actual time follows exponential and takes -

Reaction

CcmstantsN := 236.1o19

kw

Ss := 16”—m-K

d := 1.00?.cm

L := 0.0365.cm

NA := 6.022-1#.mole-1

AH r := - lS38.4@-!-mole

t p := 30”min

U(32+ 6F --> W* +02

Molecules of UOZpersamF

Thermal Conductivity of Sta

Diameter of planchette

Thickness of planchette

Avogadro’s Number

Reaction Enthalpy [exother

Plasma Processing Time

titermediate Resulti

~ , n-c?.=— S = 7964”10-5 m24

Crosssectional

NT := —

NA-r) = 3.919 .10-5 lnol Moles of U02

-AH r-qQ ,= Q = 0.033W Maximum heat I

‘P

E_tota{ := Q-t ~ E_total = 62.249 J

E.5. Vapor Pressure Correlation

Vapor pressure correlations and the related te

described in Table E-7. References to the cc

166

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Table E-7. Vapor Pressure Correlation.

Species Vapor Pressure Temperature (K)

UF6,.

UF5

UF4

UF3

UF2

UF

u

U02

U02F

U02F2

Correlation (Pa)Low High

~,521-~133.2x1O T 273 342

,3,994-W133.2x1O T 125 420

~2,6-16i400

133.2x1O 7 ‘3”02”r’Og’07 298 1309~~45_~

133.2x1O T 1543 1673

Reference

Lange and Forker (1967), p.1450,

Katz et. al. (1986) Vol. 1,p308

Jacob et. al. (1980), p. 27,

Jacob et. al, (1980), p 6I

No data Bond dissociation energy suggests p- PUF4

(Hildenbrand and Lau, 1992)

No data~71-25230

1.01X105X10 T 1480 2420 Katz e. al. (1986), Vol 1, p. 228

28.65-34:0—-5.64 *LwIOI’

106X10 3120 5000 Ohse et. al. (1979)

No data~68-15106

1.01X105X10 r 956 1000 Lauet. al (1985)- (1/g. s)*Puo2F2 at

UOF4 1000K - “ Lau et. al. (1985)

167

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E.6. Gibbs Energy Correction For Pressure And Temperature

The Gibbs free energy of formation has a pressure ~ependence (Alberty

and Silby, 1997) that depends on ‘whether the material is in the solid (or liquid)

phase, or in the gas phase. In the solid phase, the volume, V, of the material is

independent of pressure. The Gibbs energy of formation, G, is given by

G= GO+ V(p-pO) (E-19)

GO is the Gibbs energy at standard temperature (T = 298K) and pressure,

PO= 1 bar).

Taking one mole of the amorphous U02 (density - 6.8 g/cm3), the

equivalent mass is equal to the molecular weight, 270 g/mole. Using the density

and mass, V -56.25 cm3 per mole of UOZ. The chamber pressure at the lower

operating limit is 10.8 Pa, which gives the greatest error in the above equation.

The correction, in kJ/mole units repofied for Gibbs, gives

G = Go – 5.6x10-3 (kl/mole) (E-20)

to the

to the

Therefore, for solid materials, the correction is extremely small compared

typical values found for the reaction sets and can be neglected compared

standard state values. Since the reactions are with absorbed F atoms on

the surface, corrections to the Gibbs energies for

corrections either. The Gibbs free energy of F atoms

fluorine will not require

in the gas phase will be

used as an approximation.

The UF6 desorbs into the gas phase, and

applied to this gas. The correction in this case for

given by

[)G= GO+qRTln ~

P

so the ideal gas law can be

the Gibbs heat of formation is

(E-21)

Using the same values as before leads to the following correction

G = Go – 0.075(ti / mole) (E-22)

168

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Again, this comection is small for the reactions of interest and will be

neglected.

The

Therefore,

apply.

plasma gas temperature is -298K for the operating pressures used.

standard state temperature values of Gibbs energies of formation

E.7. Thermodynamic Analysis of Reactions

Thermodynamic analysis from Gibbs free energy of reaction, GR, is

determined from the Gibbs free energy of formation, Gj, of species j and the

stoichiometric coefficient, ~j, of reactants and products. ~ The stoichiometric

coefficient is positive for products and negative for reactants. Simiiariy, the

enthalpy of reaction, HR, is detemlined from the enthaipy of formation, Hj, of

each species, determines whether the reaction is exothermic (negative HR) or

endothermic (positive HR). The reaction vaiues are given as:

GR= ~vjGj (E-23)

H,=~v,Hj (E-24)J

When GR is positive, the reaction cannot proceed spontaneously but

requires energy to proceed. When GR is negative, the reaction is favorabie. The

reaction possibilities of one or two absorbed F atoms with U02 based on

combinations of U-O-F combinations (Chapter 6) is detaiied in Figure E-4. if GR

is positive (dashed iine), the reaction sequence is terminated. When GR is

negative (soiid iine), the reaction sequence is continued to the end product,

which is UF6. The uranium metai reaction with F atoms are quite different. The

initiai reaction is with a singie absorption site as shown in Figure E-5. Since no

oxygen atoms are in the reaction, oniy uranium fluorides form and there are no

unfavorable reactions.

169

Page 188: LosAlamos - International Atomic Energy Agency

XF+ IJ02

Reactions and Gibbs Free Energy (kJ mot-f)Note: dashedIiinfavorabla raatitonO or 02 raac%onprcductsnotshown

* iJF+898 , .

/ IL/~ -,/ “+664 > ~~f~

\

----

\\ 427

\\ UOZFa\

;,$;::.V&lj~~

\ -650

\Y

-112

<,4

➤ UF(3\ -223\ I\ UOF3 -f33

+282\ ,’+248, ‘%275 I

1U02F2 0 -164 U4F4

\ ‘//

‘+ ‘ ‘, -387\ -162

+@;_:~e, t~ \+29

J -368 I+ ‘;355,J&---.. uF~ > ‘“

:.-:.... .. .

Figure E-4. Reaction Sequence of F Atoms and UOZ.

Reactions and Gibbs Free Energy (kJ mb)

-1627

-2X2

/-449 UF4

/-670

UF3 > -162

UF2

/

UF5~

-661

UF~

‘m-396

49 UF ~

\ -162UF5 ~

UF6

UF6

UF6

UF6

UF6

Figure E-5. Reaction Sequence of F Atoms and U MetaL

170

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