-------------------- ~~-------~~-

Tt-1963

FFTF REACTOR CHARACTERIZATION PROGRAMABSOLUTE FISSION RATE MEASUREMENTS

•

Hanford Engineering Development LaboratoryJ.L. Fuller *

D.M. Gilliam +J.A. Grundl +

J.A. Rawlins *J.W. Daughtry *

May 1981

*HEDL

+ Center for Radiation ResearchU.S. National Bureau of Standards

Washington, D.C. 20234

DOE, RIchland, WA

Approved for Public Reiease;Furt.her Oissemina'tion Unlimited,j. j)-, ,c:-~~ ) dJ:Z) ;Z~tJ i

HANFORD ENGINEERING DEVELOPMENT LABORATORYOperated by Westinghouse Hanford Company

P.O. Box 1970 Richland, WA 99352A Subsidiary of Westinghouse Electric Corporation

Prepared for the U.S. Department of Energyunder Contract No. DE·AC14-76FF02170

;:

ABSTRACT

Absolute fission rate measurements using modified NationalBureau of Standards fission chambers were performed in theFast Flux Test Facility at two core locations for isotopicdeposits of 232Th, 233U, 235U, 238U, 237Np, 239pU, 240pU,

and 241pU. Monitor chamber results at a third locationwere analyzed to support other experiments involving passive

dosimeter fission rate determinations.

i i

~~ ---------------------,

ACKNOWLEDGMENTS

The authors wish to acknowledge the continuing supportand direction from Robert Bennett, Tom King and EdSheen throughout all phases of the work. Rory McBeath,Bruce Zimmerman and Steve Thompson helped with experi­ment preparation and conduct of the measurements.Neil Hoitink contributed to the experiment with helpfuldiscussions. Dale McGarry (NBS) helped with the conductof monitor chamber measurements during the passivedosimeter fission rate measurements in the IRT. LeeCarter performed the Monte Carlo calculations of fissionchamber scattering corrections.

iii

------------------------------ ------

CONTENTS

Page

ABSTRACT ii

ACKNOWLEDGMENTS iii

FIGURES v

TABLES vi

I. INTRODUCTION 1

II. MEASUREMENT PREPARATION 4

A. Ruggedized Absolute Fission Chamber 4

B. Fissionable Deposits 12

C. Data Acquisition System 14

D. Experiment Insert 19

III. MEASUREMENT PLAN AND PROCEDURE 22

IV. MEASUREMENT RESULTS 23

A. Data and Preliminary Analyses 26

B. Absolute Isotopic Fission Rate Results 31

C. Normalization of Results to Other RCPMeasurements 41

V. RESULTS, DISCUSSION AND CONCLUSIONS 46

VI. REFERENCES 49;:

APPENDIX A DATA ACQUISITION SOFTWARE LISTING A-l

>~APPENDIX B DATA PRELIMINARY ANALYSIS SOFTWARE LISTING B-1

APPENDIX C NBS TRANSMITTALS ON RESULTS OF CALCULATIONS C-l

APPENDIX D HEDL-CALCULATED FREE-FIELD SCATTERING CORRECTIONS 0-1

iv

FIGURES

Figure

1 FFTF Core Cross Section With IRT Location Shown.

2 Ruggedized Absolute Fission Chamber.

3 Absolute Fission Chamber Typical Differential PulseHeight Distribution.

4 Ruggedized Fission Chamber Typical Integral BiasCurves.

5 Ruggedized Fission Chamber Typical Saturation Curvesas a Function of Gamma Field Intensity.

6 Block Diagram of FFTF-RCP Absolute Fission RateData Acquisition System.

7 Photograph of FFTF-RCP Absolute Fission RateData Acquisition System.

8 Absolute Fission Chamber Experiment Insert Stalk.

9 Section Drawing of Experiment Insert InstrumentCanister.

v

Page

3

6

8

9

11

16

17

20

21

TABLES

Table

I FFTF-RCP Phase 1 Experiments

II Absolute Fission Chamber Cleaning, Bakeoutand Purging Procedures

III FFTF-RCP Absolute Fission Chamber ReferenceFission Foils

IV Descriptive Summary of RCP-AFCS Signal Cables

V Absolute Fission Chamber Use Strategy for FFTF-RCP

VI Dual Delayed Pulser Deadtime Measurement Procedure

VII RCP Absolute Fission Chamber Deposit Identification

VIII RCP Experiment 5 Data File Identification

IX RCP Absolute Fission Chamber DAS Deadtimes

X FFTF-RCP Absolute Fission Rate Deposit Se1f­Absorption Corrections

XI Fission Cross Sections Used to Determine ImpurityFission Correction Factors

XII Deposit Batch Impurity Fission Correction Factors

XIII Final Results: In-Situ Absolute Isotopic FissionRates as Referenced to 239pU Fission Rate at theFFTF Core Midplane

XIV Final Results: In-Situ Absolute Isotopic FissionRates as Referenced to 239pU Fission Rate at the FFTFUpper Axial Reflector

XV Free Field Fission Rate Correction Factors

XVI Free-Field Absolute Isotopic Fission Rates asReferenced to 239pU Fission Rate at FFTF CoreMidplane

XVII Free-Field Absolute Isotopic Fission Rates asReferenced to 239pU Fission Rate at FFTFUpper Axial Reflector

vi

Page

2

13

15

22

24

25

27

28

30

34

35

35

36

38

42

43

43

TABLE (Cont'd)

Table

XVIII FFTF-RCP Experiment 2 - Proton Recoil ChamberSpectrometer Monitor Chamber Normalization Data

XIX FFTF-RCP Experiment 3 - Proton Recoil EmulsionsMonitor Chamber Normalization Data

XX FFTF-RCP Experiment 8 - Fission Yield ExperimentMonitor-Chamber-Derived Total Fissions (In-Situ)

XXI FFTF-RCP Experiment 10 - SSTR and Passive DosimeterCalibrations Monitor-Chamber-Derived TotalFissions (In-Situ)

vii

44

45

47

48

I. INTRODUCTION

The Fast Flux Test Facility (FFTF) is a liquid-sodium-cooled test reactordesigned to irradiate LMFBR fuels and materials at prototypic temperature andflux conditions. Accurate core environment neutronics characterization isan integral part of any subsequent test evaluation. Consequently, a ReactorCharacterization Program (RCp)l was formulated to measure the important neutron­induced reaction rates in-core during reactor operation. The program consistsof three phases to be performed prior to routine operation of the facility.The first phase consisted of very low power (0-1 MW) measurements of fissionrates and neutron and gamma spectra in the core region by active and passivetechniques in a controlled temperature environment. The second phase willconsist of the irradiation of passive sensors in fuel pin cladding containedin reactor characterizers, which are designed to resemble normal reactor com­ponents as closely as possible. Second phase measurements will be performedat a power level of 4 MW (1% of full power). The final phase will consistof a similar irradiation at full reactor power. The absolute fission ratemeasurements were performed during the program's first phase.

A listing of the first phase neutronics measurements 2 is given in Table I.

The absolute fission rate measurements using special absolute fission chamberswere undertaken as Experiment 5. Run-to-run power level normalization relatingmeasurements in Experiment 5 to those of Experiments 2~ 3, 8 and 10, was accom­plished by including a IImon itor ll absolute fission chamber in each experiment.

The controlled temperature environment for these experiments was provided byan In-Reactor Thimble (IRT). This thimble was a 12.2 m (40 ft.) vertical portin the configuration of a double wall vacuum IIbottle ll in which dry N2 coolingwas also included. The sensors were operated at 70°F, even though the reactorsodium coolant outside the IRT was ata temperature of 400°F.

The IRT took the place of a fuel assembly in the centrally located core position3202 as showin in Figure 1. Fission chambers for Experiment 5 were nominallylocated at the core midplane and the upper axial reflector. Chamber insertion

1

and positioning in the IRT was accomplished using an Experiment Insert (El).Positioning data, EI design, and monitor chamber locations will be discussedin deta il in subsequent secti ons of thi s report.

TABLE IFFTF-RCP PHASE 1 EXPERIMENTS

Sequence Number2

3

4

5

8

1012

DescriptionProton recoil proportional counterProton recoil emulsionsAxially traversable fission chambersAbsolute fission chambersFission product yieldSSTR and passive dosimeter calibrationPassive dosimeter irradiation

Power LevelK <1eK <1e

0.2 - 10 kW0.5 - 2 kW

100 kW200 kW

1 MW

The RCP passive dosimeter fission rate determination goal accuracies for U andPu isotopes are in the range of 2 - 5% (10). This means that the goal measure­ment accuracies for the absolute fission chamber experiment are in the'rangeof approximately 2% or better. 2 In order to ensure the best measurement possible,a collaborative effort between HEDL and the National Bureau of Standards (NBS)Center for Radiation Research was established. NBS has performed similar mea­surements using a double fission chamber. 3 In order to adapt the NBS methodologyto the FFTF-RCP, the chamber operating characteristics were improved for opera­tion in an environment more severe than is encountered in the laboratory. Thisreport details the requi red development effort, experiment hardware desi gn,and measurement plan, as well as present the final analysis of the FFTF experi­mentdata.

2

Figure 1. FFTF Core Cross Section with IRT Location Shown.

3

II. MEASUREMENT PREPARATION

A. Ruggedized Absolute Fission Chamber

As mentioned in the first section, the NBS absolute double fission chamber wasredesigned to be more rugged and therefore more easily used in adverse environ­ments. Initial efforts in this area were performed as part of a more generalprogram in LMFBR instrumentation development. The major part of the effort,however, was undertaken in direct support of the FFTF-RCP.

The fission chamber (re)design criteria were established to meet, as a minimum,FFTF-RCP requirements. During reactor characterization a set of chambers wasto be placed in the IRT. The IRT was a vertical access port extending fromthe reactor operating deck, through the vessel head, and through the reactorcore at a position just off the center axis. Maximum thimble temperature couldreach 204°C (400°F), the liquid sodium temperature at zero power, if the instru­ment cooling system failed to keep the experiment environment at a nominal 21°C(lO°F). The capability to make measurements in gamma radiation fields greaterthan 106 R/hr was also desired.

The more conventional absolute fission chamber, as discussed in Reference 3,is a gas flow device which utilized teflon insulator components assemb1ied ina manner to provide easy access and changeout of fissionable material depositsof known composition and mass. Though suitable for laboratory or zero powerfacility experiments, use of the device in a power reactor environment requiredadditional development.

The absolute fission chamber was redesigned to be a sealed device but with thecapability to change out deposits being retained. Because of certain require­ments related to weld and seal fabrication, and to improve general resistanceto harsh environments, the wall and electrode material was respecified to bestainless steel instead of aluminum. All teflon insulator components werereplaced with ceramic counterparts. Internal component tolerances were tightenedand coaxial cable stem connections were used in order to eliminate vibration

4

induced microphonic noise - a persistent problem with the laboratory units.The mass of all components was kept to a minimum and the electrical connectionswere placed at a significant distance from the chamber to reduce scatteringeffects. For the same reason, all components were fabricated from hydrogen­free materials (as in the laboratory version). An exploded drawing of theruggedized fission chamber is presented as Figure 2. The chamber is dividedinto an upper and lower detector. Fissionable material deposits on stainlesssteel substrates are placed back-to-back in the foil retainer to form a commoncathode and inherently are described by the same spatial coordinates. Eachcollector is a split ring notched to accept the center conductor of one cableforming the stem. In this manner, the collector is removable to allow depositchangeout and microphonic noise is minimized. All internal conductors, exceptdeposit substrates, are electroplated with Au and the foil holder diameter isO.OOl-inch less than the chamber internal diameter to maintain good, nonmicro­phonic electrical contacts. Because the chamber internal component dimensionsare nearly the same as those of the laboratory version, the electron collectiontime in both devices is believed to be approximately equal, ~ 70 nsec. 3

One of the major advantages of the ruggedized fission chamber as compared tothe laboratory version is the ability to change out deposits but still havea hermetic (no gas flow) detector. This is accomplished by use of a miniaturechamber valve and a secondary top-of-chamber seal. The secondary C-seal isa commercially available component which seals the cover to the chamber flangeand is usable even after many deposit replacements. The C-seal is a lead coated,stainless steel ring. The valve assembly consists of a threaded female openingprotruding from the side of the chamber. A small annealed copper seal is locatedat the bottom of the protrusion. An allan set screw with a polished end isused to close the gas flow opening - a small hole in the side of the valveprotrusion. Once a new set of deposits are in place inside the chamber, theupper detector components are replaced and the chamber cover is loosely rein­stalled. The chamber can then be purged with counting gas and sealed. Ifoperation of the chamber at temperatures greater than 100°C is anticipated,bakeout at a more elevated temperature is necessary after a thorough cleaningof the chamber internals.

5

COVERSST

C-SEAL;--~~~~LEAD PLATED SST

~=,:;,I-WAVE SPRING WASHERSST

-8_-- SPRING SHIM. SST

COLLECTOR INSULATOR CAPALUMINA

COLLECTOR INSULATOR-----­ALUMINA

SMALL COLLECTOR RINGAu PlATED SST ----.((

FOIL RETAINER:---ll-jALUMINA

FOIL HOLDER~----tl\

Au PLATED SST "lll:S;;=';;~

FOIL INSULATOR----tALUMINA

SMALL COLLECTOR RINGAu PLATED SST

COLLECTOR-------~

Au PLATED SST """''''''''''''--

MODIFIED COLLECTORINSULATOR

ALUMINA

COLLECTORAu PlATED SST

LARGE COLLECTOR RINGAu PLATED SST

SPOT BRAZE 3 PLACES

CHAMBER ASSEMBLYSST

HEDl 1901-0'/0

SMA RECEPTACLE

.-

FIGURE 2. Ruggedized Absolute Fission Chamber.

6

The individual fission chamber components were selected based on their excep­tional tolerance to harsh environments. Gross component failure should notprove to be the limiting factor for operation to temperatures of 540°C (lOOO°F).The stem assembly is fabricated using parallel sections of commercial gradeSi02-insulated, stainless steel sheath, coaxial cable. Satisfactory performanceof this component to temperatures of 600°C and radiation doses exceeding 1016

nvt is believed possible. The alumina internal insulators should exhibit,as a minimum, similar characteristic limits. The fissionable deposits arefabricated by vacuum deposition of oxide or fluoride compounds which are charac­terized by very high melting points. Deposits of both types have been heatedto 500°C or greater with no material loss detected. 4 The deposits are discussedin detail in the next section. For chamber use at temperatures greater than300°C, an uncoated stainless steel C-seal is recommended.

Fission rate measurements using the double fission chamber are not exceptionallysensitive to system gain changes because deposit events produce pulses of rela­tively high pulse amplitude. As discussed in Reference 3 and in subsequentsections of this report, the fission fragment differential pulse height distri­bution is typified by the spectrum presented as Figure 3. The integrated countrate above Vu is corrected to determine the absolute fission rate. Integralpulse height curves, commonly referred to as integral bias curves, are oftenused to compare the operational characteristics of commercially available fission

chambers and are particularly useful in judging gain stability. Curve A ofFigure 4 is the corresponding integral bias curve for the differential spectrumof Figure 3. System gain changes can be thought to produce corresponding shiftsin Vu' the upper discriminator level, along the abscissa of either graph. Itcan be seen that with prudent selection of deposit thickness, large rate varia­tions will not occur even for appreciable gain changes.

Gain stability is directly related to hardware (preamplifier-amplifier-discrim­inator) stability, fill gas density changes, and outgassing from chamber inter­nals. The first is secondary to this discussion. The latter two need to beconsidered. The gas purge and fill procedure normally results in a slightlygreater-than-atmospheric pressure (density) fill. Gain shifts of less than -1%

7

0.87%

- HEAVY DEPOSIT196~g/cm2

-- LIGHT DEPOSIT4~g/cm2

'/--"':::'-=0I ~

IIIIIIIIIIIIIII

\1 I~ /

I" /........ /l=--+" .J .................

II •I 0.14 % ..... 50% 1

EXTRAP6LATED IFISSION PULSE I

-5 DISTRI8PTIONS I~~~:~EE~~~~10 !-_",*~I--:~_~:----::L=-_~_--:~_-4~~.u~~..u~

o m~~ ~

-210

...JWZZ«J:u

~z='ouzoenenIJ..

...J«r-or-IJ..

o -4

~ 10r­u«a::IJ..

Figure 3. Absolute Fission Chamber Typical Differential PulseHeight Distribution.

8

V'lI­z:::IoU

FISSION RATE DATA"DISCRIMINATOR LEVEL, VOLTS

lOS,.)--r-.,.2~-,---;"_~~.-,r--"';;--.---':" 0

(A) Rate Data

(C)

(E) 1, ~H!

(D) '~ll(B) (see text) hi"~

I\~, !

"' 0 L-U<LI.L---.1..--J._~--l---l._..L--J...J..1..1-."":

.2 .4 .6 .8 1.0

VIBRATION DATA DISCRIMINATORLEVEL, VOLTS

Figure 4. Ruggedized Fission Chamber Typical Integral Bias Curves.

9

per week are not difficult to attain at room temperature with the valve andseal designs previously described. Gain shifts many times greater can be com­pensated for by shaping amplifier gain readjustments just perior to measurement.Chamber outgassing problems can occur at elevated temperatures as will be dis­cussed.

A prototype ruggedized chamber was extensively tested in simulated power reactorenvironments with successful results. Studies of chamber performance underconditions of vibrational loading, high gamma irradiation and high temperaturewere completed.

The ruggedized chamber is very tolerant of microphonic environments. CurvesB, C, 0, and E of Figure 4 illustrate the typical chamber response to variouslevels of vibrational loading. These data are for the bottom detector, nofission source present, vibrational direction perpendicular to chamber centralaxis. Under 19 loading amplitude at 0 Hz (B), 15 Hz (C), 100 Hz (0) and 500Hz (E), the noise level is increased but stays well below Vu/4. Fission ratemeasurements using internal 252Cf deposits show equivalence to within a 0.2%(10) counting statistical precision. Comparative tests using the chamber labora­tory version often resulted in preamplifier pulse saturation. The ruggedizedchamber microphonic response is about the same as seen using sealed, commer­cially available fission chambers.

The ruggedized fission chamber bias saturation response as a function of gammaradiation dose rate is presented as Figure 5. The detector bias under optimumconditions is set to 100-150 volts. From the 0 R/hr data, detector bias stabilityis found to be good. However, in high gamma fields loss of ion pairs via recom­bination with secondary electrons becomes significant and saturation is seento occur only at higher bias. It is evident that care must be expercised if

the chamber is used in fields above 1 x 106 R/hr.

Prototype fission chamber operation was tested at elevated temperatures bythermal cycling and steady state measurements. Thermal cycling tests wereperformed to check chamber hermeticity under rapidly varing conditions. The

10

400200 300DETECTOR BIAS VOLTAGE

100

3000

~z:0uu.JV')

c::::u.J 20000-

V')I-

::::l0u

2 x 10 6 R/hr1000

FIGURE 5. Ruggedized Fission Chamber Typical Saturation Curves as a Functionof Gamma Field Intensity.

11

prototype chamber was cycled between 38°C and 323°C (lOO°F and 450°F) on aperiod of approximately 20 minutes for ten repetitions. The fission fragmentdifferential distribution peak position was noted on the cool side of eachcycle. No peak shifting occurred, which indicated that no gain shiftingoccurred due to chamber leakage.

Initial fission rate measurements in the laboratory at elevated temperatureyielded less than satisfactory results. In the range 120°C to 230°C, signifi­cant degradation of the pulse height distribution occurred. However, the chamber

recovered after cooling. The effect was attributed to outgassing of adsorbedimpurities, probably dominated by H20, from chamber internals. A cleaningand bakeout procedure was devised to correct this problem. These proceduresare summarized in Table II. Chamber performance improved dramatically at hightemperature with the implementation of the procedures.

Little or no fission fragmentsubsequent development tests.at room temperature and 204°C

pulse distribution distortion occurred duringLaboratory absolute fission rate measurements

(400°F) produced equivalent results.

In summary, development of the ruggedized version of the NBS double fissionchambers was successful. Performance in the worst-case, FFTF-IRT environment(204°C, 106 Rad/hr, 15-800 Hz at 19) was checked and found to be satisfactory.This effort has wider application, and it should prove straightforward to makeabsolute fission rate measurements in thermal environments up to 540°C (lOOO°F).

B. Fissionable Deposits

A very important part of the FFTF-RCP absolute fission rate measurement effortwas the specification, procurement, and assay of the fissionable deposits.A similar effort undertaken at Aerojet Nuclear Company, Coupled Fast ReactivityMeasurement Facility (CFRMF) is described in detail in Reference 3 and is indi­cative of the consideration given to deposit use.

12

TABLE II

ABSOLUTE FISSION CHAMBER CLEANING, BAKEOUT AND PURGING PROCEDURES

Cleaning1. Disassemble chamber completely except for gas valve seal.

2. Wash ceramic internals: soak in acetone for five minutes;boil in distilled water for ten minutes;wash with alcohol for fivemi'nutes;blow dry wi th air gun immedi ately afterremoval from wash.

3. Wash metallic internals: wash with acetone for five minutes;ultrasonic wash with alcohol for five minutes;blow dry with air gun immediately after removalfrom last wash.

4. Fissionable deposits are not subjected to cleaning.

5. Reassemble chamber (including deposits) without tightening/sealing cover.

Bakeout and Purging6. Purge with argon for 30-60 minutes at temperature 50-100°F higher than

anticipated operating temperature.

7. Turn off heater, continue argon purge until chamber is below 100°F.

8. Purge with P-10 for 20-30 minutes.

9. With P-10 purge continuing, seal chamber.

*for operation at room temperature, Steps 6 and 7 may De omi-tted, as well ascleaning.

13

Fifteen deposits were employed for the FFTF measurements. Most were procuredfrom the Joint Research Centre, Central Bureau for Nuclear Measurements (CBNM),Geel, Belgium. The choice of the Geel-CBNM laboratory was based on their abilityto make double-rotated vacuum evaporation deposits. The 238U deposits wereoxide deposits prepared at Los Alamos National Laboratory (LANL). One 239pu

deposit and the 24l pu deposit were made at Oak Ridge National Laboratory (ORNL).

The fissionable material deposits purchased from Geel were in the form of anhy­drous actinide fluorides. Fluorides have lower sublimation temperatures thanoxides. Fluorides also tend to deposit as single molecules while oxide mole­cules tend to form clumps as they stream from the crucible to the backing.For fluorides it is not necessary to heat the backings, and the single moleculesadhere better than clumps. The preparation of such deposits at Geel is describedin Reference 4.

A listing of the deposits, their reference mass, and impurity content is includedas Table III. A complete set of backup deposits was provided by additionalinventory at NBS. Assay of the RCP foils was accomplished by comparison toreference NBS deposits, using alpha counting and fission counting in benchmarkfields. An assay information summary is included in Appendix C. These datawere the result of assays and chemical analyses performed by at least two labora­tories (NBS, ORNL and Geel). NBS obtained fissionable material from ORNL andshipped it to Geel for deposition.

C. Data Acguisition System

The Data Acquisition System (DAS) was engineered to accommodate simultaneousinput of three double fission chambers, requiring six identical, chained countingchannels. A block diagram of the DAS is shown in Figure 6. A photograph ofthe system is presented as Figure 7. A seventh channel was included for backgroundnoise detection. The shaping amplifiers, ORTEC model 450, could also be usedin the differential input mode for common mode noise rejection, if needed.Using 0.5 ~sec differentiation and integration time constants, the resultingunipolar output pulse FWHM was typically 1.5 ~sec and the nominal countingchannel deadtime was less than 3 ~sec.

14

TABLE III

FFTF-RCP ABSOLUTE FISSION CHAMBER REFERENCE FISSION FOILS

Principle Isotope Batch Impurity CompositionIsotope Deposit ID Mass (atom percent)

232Th 02N-9 621 119 ± 2%237Np 37K-05-1 68.3 ± 1.1 %233U 23K-02-8 30.71 ± 1.5% 232U <0.6 ppm

233U 99.76231+U 0.018235U 0.009236U <1.0 ppm238U 0.21

235U 25A-03-1 30.96 ± 0.77% 231+U 0.182225A-03-2 30.91 ± 0.77% 235U 99.0829

236U 0.0353238U 0.6996

238 0 28G-5-1 735.7 ± 1.2% 231+U 0.00016U 235U 0.01755236U <0.00001238U 99.9823

238N 28NC-5-1 651.7 ± 0.9% 231+U 0.0054U 235U 0.7194238U 99.2752

239pU 49K-005-1 0.0983 ± 0.8% 238pU <0.001·49K-001-3F 1.788 ± 0.6% 239pU 99.97849K-0-3F 4.893 ± 0.6% 21+ 0pU 0.02149K-02-3F 25.33 ± 0.5% 21+lpU 0.000549K-03-2F 35.10 ± 0.5% 21+ 2pU 0.000549K-4-1 468.1 ± 0.6% 21+1+pU <0.0002

21+ 0pU 40L-2-3F 221.4 ± 0.8% 238pU 0.0109239pU 0.672721+ 0pU 98.519121+lpU 0.428921+2pU 0.367921+1+pU 0.000621+lAm 0.17

21+lpU 41 K-03-l(L) 8.71 ± 2.5% 238pU 0.001(10/13/80) 239pU 0.972

21+0pU 0.25521+lpU 98.65321+2pU 0.11821+1+pU 0.00221+ lAm 15.0

15

MASTERTIMER

INTERVALTIMER

HEDl7902-209.20

EIIIw!;

INPUT FOR6 OTHERCHANNElS

Sl SCALER

PARAllEL·TO-SERIALINTERFACE

COUNT RATEDATA

SHAPING L---JINTEGRAlAMPLIFIER ..-r-lDISCRIMINATDR I .. I

Vl = 0.40. Vpaak

FIGURE 6. Block Diagram of FFTF-RCP Absolute Fission Rate DataAcquisition System.

0\

-'.......

FIGURE 7. Photograph of FFTF-RCP Absolute Fission Rate Data Acquisition System.

Each channel was modeled after the triple scaler system employed by the NBS forsimilar measurements in the past. 3 The count rate above the lower discriminationlevel VL (see Figure 3) is called SL and above the upper discriminator VU'is called SUo These two independent integral discriminators set in the valleyof the pulse height distribution gave redundant records of the number of fissions,reducing the possibility of error due to scaler malfunction. Under normalconditions (maximum noise amplitude well below VL), the difference in the counts,SL and SU' was used to infer the number of valid fission .counts between VLand zero, on the basis of the assumption that the pulse height distributionwas flat between O~V~VU. The estimated fraction of the fission pulses in therange O~V~VU is termed the extrapolation-to-zero (etz) correction. The etzcorrection was taken from (l-SU/SL) data as will be discussed with the resultsanalyses in Section IV. The reproducibility of the (l-SU/SL) data under normalconditions was good enough that this quantity provided a reliable indicatorof any significant electronic noise above VL. The counting window of the single­channel analyzer was set on the peak of the pulse height distribution so thatthe count SGC (GC = gain check) was a sensitive monitor of gain stability.The pulse height analyzer was used to set up the triple scaler systems, particu­larly to adjust the amplifier gain so that the relative position of the dis­criminators and the peak of the fission fragment pulse height distributioncorresponded to the specification given in Figure 3. The distribution wasalso monitored to determine overall chamber performance. The use of multi­channel analyzers for primary data acquisition was not considered prudent dueto the large deadtimes associated with such units.

The DAS assembled for the FFTF-RCP measurements was comprised of seven NIMstandard scaler systems chained in series and connected to a PDP 11/05 as wellas a TTY/papertape unit. Thumbwheel data tagging modules were fabricated soall data output would be identifiable. The PDP 11 configured by TennecompInc. into their Model TP 5/11 operated in a foreground/background mode. Thus,simultaneous pulse height spectrum compilation and data acquisition programoperation was possible. The DAS was set up to collect fission fragment pulseheight spectra from all six channels during a measurement, as well as accept,format and store scaler count data and other important information (date, time,

18

------------------ -------------------------------

etc.). The software written to perform these tasks was named NIMIN and isincluded in Appendix A. Software written to perform preliminary, near real­time data analyses (program AFR and AFRS1) is included in Appendix B and willbe discussed in Section III.

D. Experiment Insert

The experiment insert (EI) was used to place and position the absolute fissionchambers, accompanying thermocouples, and signal cables into the IRT. TheEI was composed of two sections: the upper instrument stalk and the lowerinstrument canister. A simplified drawing of the stalk is presented as Figure8, and the canister as Figure 9. The canister held three detectors at anyone time at the following core axial locations:

011 (core midplane)+21.25 11 (upper axial reflector)-14.75 11 (lower core, monitor

chamber position).

The stalk was the tubular extension for handling the canister, routing signalcables, locating cable penetration seal plug, and locating a sodium seal plug(in case of IRT rupture). The assembled EI was approximately 40-feet longterminating at one end on IRT bottom and the other end at the operatingdeck level.

The coaxial signal cables in the canister were metal-sheathed, Si02 insulated,therefore radiation and temperature tolerant. The cables in the stalk wereteflon insulated, having adequate radiation and temperature (250°C) tolerancefor out-of-core use. The characteristics of these cables, including the shortsections comprising the absolute fission chamber stem, are listed in TableIV.

19

METERING TUBE

--HCDA PLUG72.0

__TRANSITION TUBE

__ SHIELD PLUG

.,. ,, ,

76.625

315.00r-':::'":I ......-- SUPPORT COLLAR

--

in inches)

HEDL 7902-209. 1

FIGURE 8. Absolute Fission Chamber Experimental Insert Stalk.

20

;-0.1;._ ..~:1 II, Ir-- --\

,'e a" r EL 516'-5.88" REF.

UPPER TUBE __________

MI EL 513'-10.25" REF.

~

...-.mnroo

~lDJ,L

I I EL 512'-3.25" REF.

7.00"

jI~ TOP OF CORE

EL 511' -5 .00" REF.

1-

Il-

himo

I~W

+21 .25"(REF LECTOR REG ION)CHAMBER

CHAMBER SIGNAL II ~II

CABLE

THERMOCOUPLE --_.--i---<

CABLE

II EL 510' -6 .00" REF.

JIi-o

CORE MID-PLANE U~

CHAMBER ~

CORE MI D-PLAN E1-1---EL 509'-11.00" REF.

'---'

CENTER TUBE -

I I

LOWER TUBE ·1::I II II

~III

"II,

I,~ ~ EL 506'-5.88" REF.I r-~L .Te

HEDL 7902-194.10

Figure 9. Section Drawing of Experiment InsertInstrument Cannister.

OOE- Richland, WA

TABLE IVDESCRIPTIVE SUMMARY OF RCP-AFCS SIGNAL CABLES

Capaci-tance Impedance

Location/Use Type/Description Insulation (pf/ft) (ohms)detector stem hardline coaxial 3.91 mm 00 Si02 16 97assembliesinstrument hardline coaxial 3.91 mm 00 Si02 16 97canisterinstrument RG l80B/U Teflon 15 95stalk 3.68 mm 00 x 13.7 m long

(0.145 11 00 x 45 ft long)

The EI was assembled and tested under prototypic conditions prior to use in theFFTF. The results of these tests are discussed in Reference 5. This effortwas useful in that two problems were shown to exist: 1) RF and ground loopnoise rejection methods had to be incorporated into the system, and 2) allowancefor differential linear expansion of stalk and cable had to be made even thoughteflon and stainless steel expansion coefficients are nearly equal.

III. MEASUREMENT PLAN AND PROCEDURE

Two considerations in planning the measurements were deadtime and statisticaluncertainty minimization. In order to achieve overall measurement uncertaintyof about 2% in a situation where deposit mass uncertainty may approach thismagnitude, a goal of 0.1% or less for deadtime and statistical uncertaintieswas established. With regard to deadtime losses, using a system of nominal re­solving time of 3 ~sec, deposit masses were selected and reactor power specifiedto keep counting rates below ~2500 cps. The goal statistical uncertainty wasachieved by specifying counting time to accumulate several million counts.

The strategy devised to use all isotopes at both core midplane and upper axialreflector in Experiment 5, and appropriate monitor chambers for Experiments2, 3, 5, 8, and 10, is summaried in Table V. Eight fission chambers, as des­cribed in Section II A., were fabricated and assembled in order to implement

22

the plan with minimum reactor down time. The corresponding chamber identifica­tion numbers are included in the table. As indicated in Section II C, sixidentical channels were included in the OAS for simultaneous counting usingthree double fission chambers.

Considerable effort was expended before, during, and after the FFTF measurements,to measure counting channel deadtime accurately. NBS normally employs a varia­tion of the two-source method using a source attenuator in an access port totheir research reactor. The analyzer-pulser method was successfully appliedat HEOL. A third, much simpler method was later devised based on a dual delayed­pulse generator (Canberra l407P or equivalent). Oual-pulser results agreedwith the two more involved methods. Because deadtime depends on discriminatorlevel in RC-shaped, leading edge discrimination networks and because in thisexperiment optimization required non-normal discriminator level settings, thedual-pulser method proved useful. The procedure employed using the doublepulser to measure deadtimes is outlined in Table VI. The final results werecorrected by 0.31%, a factor calculated by comparing the dual-pulser-measuredTO and the deadtime determinable by the two-source method combining resultsfrom Experiments 8 and 10.

IV. MEASUREMENT RESULTS

The results presentation is divided into three sections. The results fromExperiment 5, the actual isotopic fission rate measurement experiment, arepresented in Section IV A and IV B. The normalization measurements, usingthe monitor chambers, are presented in Section IV C. The preliminary resultswere calculated using the OAS computer and the analysis code AFR (and subroutineAFRS1) as listed in Appendix B. AFR took raw total count data from up to tendeterminations, computed a mean rate, corrected it for deadtime and added theetz correction. In order to determine the absolute fission rate and its asso­ciated uncertainty, further corrections to the preliminary data were required.The statistical uncertainty computed using AFR was included, as were the depositmass measurement uncertainties, the correction for fissions in minor isotopicconstituents of each deposit, and the deposit self-absorption correction. These

23

~ or ~ ...

TABLE V

ABSOLUTE FISSION CHAMBER USE STRATEGY FOR FFTF-RCP

~_erimen! Run Chamber JocatiQ!!. Chamber 10 _~_}s()tojle-IQ-!'1~~~ ___~__ Reac tor yow,"-,: Expected~unt Rate Counting Time2-3 moni tor (+21") RCP 7 "'P.,(49K-4-1 )468.1 Jl9 subcritica 1 1-10

blank

reflector (+21") 4 2;QPu(40L-2-:lF)221.4 0.9 kW 536 105 min2;

I P.,(41K-03-1 (L))8.71 (10/13/81 ) 351

midplane (0") 1 2351J( 25A-03-1 ) 30.96 13102"Pu(49K-03-2F)35.10 1394

monitor (-15") 8 2"Pu(49K-02-3F)25.33 8302"Pu(49K-0-3F)4.893 160

refl ector 5 237Np(37K-05_1 )68.3 2 kW 445 60 min236NIJ(28NC-5-1 )651.7 1090

midplane 3 2380H(28G-5-1 )735.7 2846232T (02N-9)621 545

moni tor 8 3320641

reflector 2 2"1J(25A-03-2)30.91 0.65 kl, 827 105 min2"1J(23K-02-8)30.71 1201

N1910..j::> midplane 4

483

moni tor 8 830160

refl ector 1 0.65 kW 830 60 min190

midplane 2 1310

1890

monitor 8 830160

reflector 3 462 150 min83

midplane 5 20503263

monitor 8 3320641

8 & 10 monitor (-15") 6 23'P.,(49K-OOl-3F)1.7B8 100 kW(8) 8500(8) 2 hour (8)200 kW(10) 17,000(10) 4 hour (l0)

2"Pu(49K-005-1)0.0983 640(8)1300(10)

TABLE VI

DUAL DELAYED PULSER DEADTIME MEASUREMENT PROCEDURE

1. Display detector pulse-height spectrum and adjust gain

to optimize according to Figure 3.

2. Adjust discriminator levels as would be accomplished for

an actual rate measurement using analyzer.

3. Determine mean pulse height for particular spectrum.

4. Adjust both primary and delayed pulse to mean pulse

height level.

5. Starting with delayed pulse widely separated from primarypulse, decrease pulse separation until counting rate de­

creases by one half.

6. Measure this delay between beginning of two pulses at

input of shaping amplifier.

7. Measure width of primary pulse at discriminator level

at output of shaping amplifier.

8. Average of time delay and pulse width a good measure ofsystem mean deadtime. Former will be greater than latter.

The preamp pulse time delay is believed to be too con­servative an estimate because it does not take into account

possibility of very large pulse starting after a smallpulse tripping the discriminator first. The pulse widthmeasurement with the double pulser yields a value somewhatshorter than found using more sophisticated methods in

some cases.

25

all will be discussed in more detail in Section IV.B. Note thatfree-field rates were also determined by including a chamber scattering correc­tion. The goal accuracies relate, however, to the in-situ results.

A. Data and Preliminary Analyses

Data acquisition according to the experiment plan outlined in Table III necessi­tated data set identification coding and deposit identification coding. Forfurther reference, the coding descriptions are reported here. With regardto the fissionable deposits, the thumbwheel data identification modules werenumeric only, so the alphanumeric deposit 10 numbers were converted as listedin Table VII. With regard to the data sets, which were stored on disketteswith backup and archived, the 10 codes were formulated according to a Month­Day-R-Sequence-# Determinations. Corresponding spectra sets replaced R withan H and deleted the number of determinations. The data sets obtained duringthe FFTF-RCP are described and identified in Table VIII (refer to Table III).

The DAS program NIMIN facilitated data acquisition, labeling, and storage.Between experiment runs, the program AFR and its detached subroutine, AFRS1,were used to perform preliminary data analyses. AFRjAFRSl output for Experiment5, Run 1, is included in Appendix B as a sample. The output consists of alisting of the important measurement parameters, deadtime-corrected rates,count rate ratios for each determination, the deadtime correction used, andexperimental and theoretical standard deviations. The mean rate is correctedfor etz and the "corrected" fission rate is presented. The preliminary ratesare corrected only for deadtime and etz. The associated uncertainty resultsfrom combining the larger of the mean experimental or theoretical standarddeviation, the uncertainty due to deadtime determination uncertainty, and thecalculated etz uncertainty. In dividing total counts, CK, (K=L,U,GC) by countingtime, T, to yield a rate, any uncertainty in specified counting time was neglectedas it was less than 0.001%.

The mean deadtime, TK, determined for each channel (component serial numberson record) are listed in Table IX. These values were determined using the

26

TABLE VII

RCP ABSOLUTE FISSION CHAMBER DEPOSIT IDENTIFICATION

ChamberMass Placement

Numeric10

925031949032925032923028

928851999029994023941031

937051992851490013490051994941999999

949023994903

8T8B

RCP 1 top1 bottom2T2B

3T3B

4T4B

5T5B

6T6B

7T

25.334.893

30.96 ].1935.1030.9130.71

735.7621221 .4

8. 71 (1 0/13/ 80 )68.3

651.71.7880.0983

461.8

Isotope235U239pU235U233U

238DU232Th2 40 pU241pU237Np238NU239 Pu239pU239 Pu

NBS 10

25A-03-149K-03-2F

25A-03-223K-02-8

28G-5-102N-9

40L-2-3F41 K-03-l(L)

37K-05-128NG-5-1

49K-00l-3F49K-005-1

49K-4-1(blank)49K-02-3F49K-0-3F

27

TABLE VIII

RCP EXPERIMENT 5 DATA FILE IDENTI FICATION

Archived Data ID Number0l2R0Hl5 '

0l2R0205012R03100l2R2106

0l2R22100l3R3105

0l3R32100l3R33050l3R4105

013R4205014R5105

0l4R52100l4R53100l4R5410

O "t" 1eSCrl p lon

10/12/81 Run 1CMP: 235/239 UAR: 240/241first accumulation, 5 determinationssecond accumulation of Run 1third accumulation of Run 110/12/81 Run 2CMP: 2380/232 UAR: 237/238Nfirst accumulation, 6 determinationssecond accumulation of Run 210/13/81 Run 3CMP: 240/241 UAR: 235/233first accumulation, 5 determinationssecond accumulation Run 3third accumulation Run 310/13/81 Run 4CMP: 235/233 UAR: 235/239first accumulation, 5 determinationssecond accumulation Run 410/14/81 Run 5CMP: 237/238N UAR: 2380/232first accumulation, 5 determinationssecond accumulation, Run 5third accumulation, Run 5fourth accumulatinn. Run 5

lRefer to Table III for additional information.

28

procedure described in Section III. Data pertaining to three additional channelsassembled for use during Experiments 8 and 10 are also included. An estimateduncertainty of ±0.2 ~sec was assigned to these values. Because all the measuredrates were low «5000 cps) a linear approximation for the deadtime correctionwas applied to determine the corrected count rate SK:

(1 )

where RK denotes the uncorrected count rate, CK/T. All rates were calculatedand thedeadtime correction was applied before averaging. For Experiment 5,deadtime corrections were 1% or less; thus the maximum expected uncertaintycontribution to the final absolute fission rate data was about 0.1%.

Several standard deviations were calculated for N repetitions and includedin the pre1}minary data output. They are defined as follows:

experimental standard deviation ~ s(SK) =N

2:j=l

N-1

1/2

(2)

predicted standard deviations ~ SIGMA, where

and mean values of the above, where

s (SK)s Mean = ---'--

iN

29

(3)

(4)

(5)

(6)

'<

TABLE IX

RCP ABSOLUTE FISSION CHAMBER DAS DEADTIMES

'('&'(' '("&'(" '(L,U=1.0031 (( T1h")/2 I'(" TGC =1.0031(('(I+T")/2)Channel L U L U ((T 1+'(" )/2) '(GC GC ((T I+T" )/2)

1 2.15 l-lsec 2.32 2.235 2.24 1.62 1.94 1.780 1. 782 2.05 2.30 2.175 2.18 1.62 1.92 1.770 1.783 2.18 2.41 2.295 2.30 1.64 1.92 1.780 1. 784 2.08 2.31 2.195 2.20 1.58 1.88 1.730 1. 745 2.10 2.36 2.230 2.24 1.61 1.92 1.765 1.776 2.10 2.30 2.200 2.21 1.61 1.92 1.765 1.77

w Xl 2.02 2.28 2.150 2.160

X2 2.07 2.32 2.195 2.20HP 2.08 2.28 2.180 2.19

T1 = measured at VL ~ Vu level using output pulses from shaping amplifier.Til = measured at V=O level using input pulses to shaping amplifier.

SIG Mean = SIGMA()IN

(7)

Before the corrected (preliminary) rates were calculated using the AFCS DASprogram AFR, the etz correction and associated uncertainty were determined.The etz correction, ETZ, is described in Reference 3, and was calculated using

(8)

For these measurements VL/Vu = 0.80. The statistical uncertainty in specifyingETZ was taken as five times the larger of either s Mean of SIG Mean of theSL/SU set of any set of determinations. In computing the total ETZ uncertainty,27% of the final correction was summed in quadrature with the statistical partin order to account for systematic error (to be consistent with Reference 3).

The preliminary corrected rates were then calculated from the expression:

Preliminary corrected rate ~ CR = ETZoSU (9)

for each accumulation set. The total uncertainty associated with the prelim­inary corrected rates was calculated by taking the square root of the sum ofthe squares of uncertainties associated with statistical uncertainty (largerof s Mean or SIG Mean of SU)' the etz correction, and the deadtime correction.

Sample output of the AFR analysis code is presented in Appendix B, in the formof output for the 012R~1~5 measurement. Data from the complete preliminaryanalysis set will be used in the next section, where appropriate, to explainand present the calculation of the final results.

B. Absolute Isotopic Fission Rate Results

The work sheets used to generate the final results from the AFR analyses andfoil assay data are included in Appendix C. In generating the final results,the mean uncorrected (except for deadtime) rates from the AFR code were averaged

31

and the statistical uncertainty in the mean value was taken as the mean predictedstandard deviation. It was considered inappropriate to use the experimentaluncertainty values, which were generally greater due to fluctuations in reactor

power.

The data and expressions used to generate the statistical uncertainties, dead­time corrections and uncertainties, and etz corrections and uncertainties(included as part of the AFR code) were presented in the previous section.In order to compute the final results, corrections and uncertainties for depositself-absorption and fissions in impurity constituents were made, and the deposit

mass assay uncertainties were factored in.

The correction for fission fragment absorption in the deposit was taken tobe t/2R, where t is the thickness of the deposit in ~g/cm2, and R is the average

fission fragment range in the deposit material. The reference range used wasthat for U30S' 7.74 ± 0.90 ~g u30S/cm2.3 In Reference 3, this value was correctedfor the difference in oxygen content for actinide dioxide by assuming thatthe range is proportional to ~ where A is the effective atomic mass evaluated

1

according to the expression I.A = E n.A./E n.A.2 (n. are the atom fractions) .. JJ.JJ JJ J 2

The resulting corrections were found to be 0.69% per 100-~g U/cm for U02'and 0.66% per 100-~g Pu/cm2 for Pu02. The values were not corrected for thelighter fluoride deposits used in the FFTF-RCP because the difference was con­sidered negligible. In the case of the thicker 232Th , 237Np , and 240 pu deposits,

the eff~ctive atomic mass used was calculated using fluoride parameters. Thesecorrections were 0.96% per 100-~g Np/cm2 for NpF4 and per 100-~g Th/cm2 forThF4, and O.SO% per 100-~g Pu/cm2 for PuF3. The estimated uncertainty in theabsorption correction is taken to be 25% of the correction or 0.35%, whicheveris larger. The non-zero floor on this uncertainty is necessary because surfaceroughness and diffusion of fissionable material into the platinum substratecould dominate the fragment absorption processes for light deposits. A signifi­cant fraction of the fragments that are emitted nearly parallel to the deposit

plane may be scattered enough to affect the absorption probability and thefission pulse-height distribution in the very low pulse-height range. However,only the difference in the in-scatter and out-scatter would affect the absolute

32

efficiency. The net scattering effect is expected to be slightly biased towardscattering into the active volume of the chamber, but this is compensated forby flat extrapolation of the pulse-height distribution. Hence, no adjustmentfor fragment scattering was made. The self-absorption correction for eachdeposit is listed in Table X.

Before the correction for fissions in minor isotopic constituents was performed,the preliminary rates (corrected for deadtime and etz) were corrected for self­absorption and normalized to the deposit absolute mass. The associated uncer­tainties in these corrections plus the counting statistical uncertainty werecombined to determine the total uncertainty (square root of the sum of thesquares).

The results were then corrected for impurity fissions using an iterative process.The correction factor for fissions for impurity isotopes i I for a deposit ofprimary isotopic composition PI was found using the expression

fimpurity fissions = __-,.n,Lp_CY'-p_---;ocorrection factor f fL:n.cy· + n a

ill P P

(10)

where n represents atom fraction and a the microscopic fission cross sections.Deposit composition data are listed in Table III. The cross sections usedare listed in Table XI. The iterative process was begun by calculating thecorrection factors for 233U, 235U, and 239 pu . Rates for threshold isotopes

were then calculated, with experimental rates for fissile constituents. Thisprocess was then repeated at least twice, always using current values for eachcalculation. The final impurity correction results are summarized in Table

XII (see Appendix C for details).

The final absolute isotopic fission rate results as measured during RCP Experi­ment 5 are presented as spectral indices in Table XIII for core midplane (CMP)and Table XIV for the upper axial reflector (UAR). These values are in-situvalues, that is, they have not been corrected for chamber scattering of reactorneutrons. The spectral index is a spectrum averaged microscopic cross section

33

--------~~~~~~~~~~~~--

TABLE X

FFTF-RCP ABSOLUTE FISSION RATE DEPOSITSELF-ABSORPTION CORRECTIONS

Deposit25A-03-149K-03-2F

2~A-03-2

23K-02-828G-5-102N-940L-2-3F41 K-03-1 (L) 1

37K-05-128NC-5-149K-001-3F49K-005-149K-4-149K-02-3F49K-O-3F

Fission ChamberRCP lT

lB2T2B3T3B4T4B5T5B6T6B7T8T8B

Self-AbsorptionCorrection

1.00171.00181.00171 .00171.04011.04711.0140

1.00541.00521.03581.00011 .00001.02461.00131.0003

1self-absorption relatively high due to gold cover layer.

34

TABLE XI

FISSION CROSS SECTIONS USED TO DETERMINEIMPURITY FISSION CORRECTION FACTORSl

Isotope of (CMP) of (UAR)233U 2.72 ± 10% barns 6.33 ± 20%234U .321 ± 20% 0.1999 ± 30%235U 2.02 ± 5% 3.98 ± 10%236U 0.101 ± 20% 0.0466 ± 30%238U 0.0446 ± 10% 0.0214 ± 20%239pu 1.915 ± 5% 3.826 ± 10%240pu 0.381 ± 10% 0.287 ± 20%241 pu 2.57 ± 10% 5.93 ± 20%242pu 0.297 ± 20% 0.187 ± 30%244pu 0.4 ± 100%' 0.3 ± 100%241 Am 0.276 ± 20% 0.191 ± 30%

lCross sections are FFTF spectrum averaged and were used for theinitial part of an iterative procedure as explained in the text.

TABLE XII

DEPOSIT BATCH IMPURITY FISSION CORRECTION FACTORS

Batch CMP Correction Factor UAR Correction Factor

23K 0.99989 ± .001% 0.99992 ± .001%

25A 0.99954 ± .006% 0.99987 ± .002%

28G 0.99203 ± .014% 0.971 05± .051 ~~

28NC 0.7502 ± .49% 0.4330 ± 3%

40L 0.9368 ± .12% 0.8477 ± .26%

41 K 0.9765 ± .35% 0.9885 ± .18%

49K 0.99995 ± <.001% 0.99998 ± <.001%

35

PercentFractional Uncertainties l

0.09 statistical0.05 deadtime0.16 etz0.35 self-absorption1.5 mass0.001 impurity fission1.55 subtotal

-03-10.050.060.140.350.770.0060.860.050.070.810.351.150.0141.450.040.090.770.350.951. 161.720.050.060.150.350.50.0010.63

±1.1%

±1.8%

±1.6%

TotalUncertainty

±1.7% (1o)

1.038

0.0227

0.0226

1.

FINAL RESULTS: IN-SITU ABSOLUTE ISOTOPIC FISSIONRATES AS REFERENCED TO 239PU FISSION RATE AT THE

FFTF CORE MIDPLANESpectral Index

°f(I)/of(239pu )

1.513Isotope233U

Normal U

235U(25A.,.03-l)

1

Summed in quadrature with ±0.63% uncertainty of 49K-03-2F at CMP. Note thatquadrature sum of fractional errors is not,truly independent of 239pU totalerror, so the total spectral index error reported here is an upper bound value.

36

TABLE XI II(continued)

PercentFractional Uncertainties l

0.060.070.880.350.80.121.25

0.080.040.240.352.50.352.580.040.080.220.351.1T"":T80.0950.091.231.182.02.63

±1.3%

±2.7%

±2.7%

TotalUncertainty

±1.4%

0.00556

1.36

0.1828

FINAL RESULTS: IN-SITU ABSOLUTE ISOTOPIC FISSIONRATES AS REFERENCED TO 239PU FISSION RATE AT THE

F.FTF CORE MIDPLANESpectral Index

239 )0' f ( 1) /0' f ( Pu

0.2018

237 Np

Isotope240pu

37

TABLE XIV

FINAL RESULTS: IN-SITU ABSOLUTE ISOTOPIC FISSIONRATES AS REFERENCED TO 239PU FISSION RATEl AT THE

FFTF UPPER AXIAL REFLECTORSpectral Index

239 Total PercentIsotope crf (I) / crf ( PU) Uncertainty Fractional Uncertainties2

.. 233U 1.513 ±1.7% (1 (j) ±0.06 statistical0.05 deadtime0.12 etz0.35 self-absorption1.5 mass0.001 impurity fission1.55 subtotal

235u 1 .015 ±1.1 % -03-10.110.030.180.350.770.0020.87

238U 0.00598 ±3.4% 0.070.070.810.351.150.0511.45

Normal U 0.00561 ±4.4% 0.080.090.770.350.952.90

,~ 3.17239pu 1. 0.11

0.03. 0.22...0.350.50.0010.66

lThe ratio of the UAR reference 239pu rate to that used in Table XI at coremidplane equals 0.671 ± 0.91%.

2Not listed is ±3.0% estimated fractional systematic error in fertile isotopemeasurements in UAR included in total uncertainty values.

38

TABLE XIV(continued)

0.060.040.990.350.80.261.340.070.030.430.352.50.182.570.0850.090.340.351.11.21

0.160.071.871. 182.02.98

PercentFractional Uncertainties

±4.3%

±3.3%

±2.7%

±3.3%

TotalUncerta i nty

0.00145

0.0604

1.50

FINAL RESULTS: IN-SITU ABSOLUTE ISOTOPIC FISSIONRATES AS REFERENCED TO 239PU FISSION RATE 2 AT THE

FFTF UPPER AXIAL REFLECTORSpectral Index

239C1f(I)/C1f ( Pu)

0.0761

241 pu

Isotope240pu

."..

39

-- ----_. __._------------.....,

ratio, that is, a rate normalized to a reference rate but compensated for differ­ences in deposit mass and atomic weight. The spectral index of isotopereferenced to isotope 2 is found from the measured fission rate FRl and FR2,as follows:

(11 )

.,

where A is the atomic weight and Mthe deposit mass. In Appendix C, the resultswere computed in terms of a calibration factor relating 239pu fission rate

to reactor power. This value is imprecise at this time, therefore, the alter­nate form of reporting was chosen. In Table XIII and XIV, the total uncer­tainty components have been broken down.

As is seen from the Experiment 5 plan outlined in Table V, the runs withinthis experiment were performed at various reactor power levels. The monitorchamber count rates were used for run-to-run power level normalization.

The results for 238U and Normal U in the upper axial reflector (Table XIV)differ from each other by more than the reported fractional uncertainty sum.The midplane results from the two deposits are in agreement, however. Thepossibility of radial and axial gradients combined with different chamber place­ment in the upper axial reflector for the two deposits was investigated. Reactionrate gradients from a three-dimensional diffusion theory calculation performedduring pre-experment planning were examined, and the calculated reaction rategradients were too small to explain the discrepancy. As of this writing, thedisagreement is not completely resolved. There is the possibility that signi­ficant streaming may have occurred vertically along annular gaps between IRTand/or EI walls, something not determinable via diffusion theory calculations .A ±3.0% fractional systematic error was thusly figured into the fertile isotopetotal uncertainty for the UAR results. For comparison purposes with otherIRT experiments requlrlng fissions/gram for 238U, the results from the depleted

uranium will be used.

40

In-situ fission rate data were required ~o provide the absolute basis for passivedosimeter fission rate determination using dosimeters in dummy chambers. Tocompare results with future reactor neutronics calculations, which may be unableto model the fission chamber, the fission rates must be corrected for neutronscattering in the chamber material. Scattering correction factors were calcu­lated using a Monte Carlo code (see Appendix D for details) for 239pu and 238Uat the midplane and upper axial reflector locations. The 239 pu factors wereapplied to all fissile deposits, and the 238U factors were applied to all other

(threshold reaction) deposits. Table XV lists the multiplicative correctionfactors and associated uncertainties from the Monte Carlo runs. Spectral indicescorrected for chamber scattering are presented in Table XVI and XVII.

C. Normalization of Results to Other RCP Measurements

Just as the runs within Experiment 5 were normalized to one another using themonitor chamber, so too were the various experiment measurements listed inTable I. Monitor chambers were used (1) to normalize proton recoil experimentdata (IRT Experiments 2 and 3) to 239pu fission rate, and (2) to normalizepassive fission dosimeter irradiations (IRT Experiments 8 and 10) to 239pu

total fissions/gram.

Fission chamber RCP 7 was used in the +21" UAR position for monitoring duringExperiment 2. 239pu deposit 49K-4-1 (mass 468.1 ~g ± 0.6%) was loaded in the

top position, and a blank in the bottom (for background noise detection). Thecorrected measured rate data for this experiment are provided in Table XVIII.Chamber RCP 7 was used in the same manner during Experiment 3 and the resultsare similarly reported in Table XIX. Because of the low counting rates inboth these experiments, the ETZ correction was deduced from a weighted averageover all four runs according to the inverse square of the mean standard deviationin SL/SU for each run, and the systematic part of the associated error wastaken as 40% of the correction.

Fission chamber RCP 6 was used in the -15" (core bottom) monitor position forExperiments 8 and 10. Monitor-chamber-determined 239pu fission rates were

41

,I

- ----------_.._--~~~~~~~~~~~---

TABLE XVFREE-FIELD FISSION RATE CORRECTION FACTORS*

Isotope Core Midplane Upper Axial Reflector233U .991 ± 1.2% (1 cr) .972 ± 1.4%235U .991 ± 1.2% .972 ± 1.4%238U 1.017±1.1% 1.033 ± 1.3%239pu .991 ± 1.2% .972 ± 1.4%240pu 1.017 ± 1.1% 1.033 ± 1.3%241 pu .991 ± 1.2% .972 ± 1.4%237NP 1.017±1.1% 1.033 ± 1.3%232Th 1.017±1.1% 1.033 ± 1.3%

*Multiply in-situ isotopic fission rate by correction factorto obtain free-field fission rate.

42

~------ -----~--------------

TABLE XVI

±3.2%

±2.1 %±2.7%

±2.1 %

±2.3%

Total Uncertainty±1.7% (la)

±1.1 %

±2.3%

FREE-FIELD ABSOLUTE ISOTOPIC FISSION RATESAS REFERENCED TO 239PU FISSIDN RATE AT FFTF

CORE MIDPLANESpectra1 Index

239af ( I) / af ( Pu)

1.5131.038

0.02330.0232

1.

0.20711.36

0.18760.00571

Isotope233U235U238

U

Normal U239pu240pu241 pu237

NP232Th

TABLE XVII

± 4.8%

±2.7%

±4.7%±3.8%

±3.8%

±3.9%±1 .1%

Total Uncertainty±1.7% (la)

FREE-FIELD ABSOLUTE ISOTOPIC FISSION RATESAS REFERENCED TO 239PU FISSION RATE AT FFTF

UPPER AXIAL REFLECTORSpectral Index

239af(I}/af ( Pu}

1.5131.015

0.00636

0.00596

1.

0.0809

1.50

0.06420.00155

Isotope233U235U238

U

43

~...., ,.

TABLE XVIII

FFTF-RCP EXPERIMENT 2 - PROTON RECOIL CHAMBER SPECTROMETERMONITOR CHAMBER NORMALIZATION DATA

~

Correction FactorsControl Rod

Confi gura ti on3 primaries @23.5 in.6 secondaries fully

inserted

3 primaries @36 in.6 secondaries @12 in.

..j::>

..j::>

Run ID2271A140

2281B156

Mean AbsoluteFiss ion Ra te 1 , 2

2.63xlO- 3f/S/].1g239

2.06xlO- 2f/s/].1g239

TotalUncerta i nty

±2.1% (10)

±2.0%

deadtime:HZ:sel f-absorption:impurity fissions:

deadtime:HZ:self-absorption:impurity fissions:

1.00000261.04371.02460.9999

1.00002071.04371.02460.9999

Percent FractionalUncertainties

0.87 statisticaldeadtime

1.75 ETZ0.62 self-absorption0.6 mass<.001 impurity fissions

0.22 statisticaldeadtime

1.75 ETZ0.62 self-absorption0.6 mass<.001 impurity fissions

1

Monitor chamber position at +21 11 above core midplane (upper axial reflector).2

Deposit used was 49K!,"4-1 @468.1 ].1g ± 0.6% 239pU.

r

TABLE XIX

FFTF-RCP EXPERIMENT 3 -.PROTON RECOIL EMULSIONSMONITOR CHAMBER NORMALIZATION DATA

Control Rod Mean Absolute TotalCo nfi gura ti 0 n Run ID Fiss ion Ra te Uncerta i nty Correction Factors

primaries fully in- 2282B18 1.69xlO-3f/s/~g239 ± 3.4% (lcr) deadtime: 1.0000018serted ETZ: 1.0437secondaries fully self-absorption: 1.0246inserted impurity fissions: 0.9999

3 primaries @36" 2282C53 5.21xlO-3f/s/~g239 ± 2.1% deadtime: 1.0000052secondaries fully ETZ: 1.0437

self-absorption: 1.0246inserted impurity fissions: 0.9999.j:>.(J1

Percent FractionalUncertainties

2.7 statisticaldeadtime

1.79 ETZ0.62 self-absorption0.6 mass<.001 impurity fissions

0.87 statisticaldeadtime

1.75 ETZ0.62 self-absorption0.6 mass<.001 impurity fissions

itt~ \- ~

then normalized to those obtained using RCP 8 during experiment 5. This quanti­tative comparison was used to specify the total fissions/~g for all isotopesat the CMP and UAR positions for the passive irradiations. RCP 6 was loadedwith 239pu deposits 49K-001-3F (1.78 ~g ± 0.6%) and 49K-005-1 (0.0983 ~g

± 0.8%), top and bottom, respectively. The AFCS data acquisition system describedearlier in this report was augmented with eight-decade scalers which were notinterrupted during the entire irradiation ion order to determine total fissions.The final results for these two measurements are presented as Table XX andXXI.

V. RESULTS, DISCUSSION AND CONCLUSIONS

Absolute fission rate measurements, using modified NBS absolute fission chamberswith isotopic fissionable deposits, were successfully completed in the FFTFIRT during acceptance testing. The goal of 2-5% accuracy fission rate mappingin special characterizer assemblies in later phases of the Reactor Character­ization Program required a careful series of passive dosimeter calibrationmeasurements in the IRT.

The core mid-plane results, extrapolated to power levels in passive sensorexperiments (Table XX and XXI), had final uncertainties in the range 0.9% to2.7%. This range of uncertainties is small compared with other uncertaintiesinherent in passive dosimeter radiometric fission rate determinations. Theresults obtained in the upper chamber, which was in a relatively softer neutronspectrum, were in the same range as the core midplane results for the fissiledeposits, but were larger (3-5%) for the threshold type deposits. The largeruncertainties are a result of a measured discrepancy between the 238U fissionra te resu 1ts obta i ned from two depos its. However, the primary purpose of theupper chamber measurements was to investigate possible neutron spectrum depen­dence of the fission product yields. Threshold type fissionable isotopes arenot expected to exhibit neutron energy dependence, so the midplane resultssatisfy programmatic requirements for non-fissile samples.

46

TABLE XX

FFTF-RCP EXPERIMENT 8 - FISSION YIELD EXPERIMENTMONITOR-CHAMBER-DERIVED TOTAL FISSIONS (IN SITU)

CMP Total In-Situ UAR Total In-SituIsotope Fissions Fissions233U 1.284 x 108 f /1l9 ± 1.8% (l a) 8.611 x 107 ± 1.8%235U 8.734 X 107 ± 1.2% 5.74 X 107 ± 1.2%

238U* 1.882 X 106 ± 1.7% 3.33 X 105 ± 3.4%239pu 8.270 X 107 ± 0.9% 5.548 X 107 ± 0.9%240pu 1.662 X 107 ± 1.5% 4.203 X 106 ± 3.4%241 pu 1.113 X 108 ± 2.7% 8.252 X 107 ± 2.7%237Np 1.525 X 107 ±1.5% 3.381 X 106 ± 3.4%232Th 4.74 X 105 ± 2.6% 8.31 X 104 ± 4.2%

*Data from depleted uranium deposit.

47

TABLE XXI

FFTF-RCP EXPERIMENT 10 - SSTR AND PASSIVE DOSIMETER CALIBRATIONSMONITOR-CHAMBER-DERIVED TOTAL FISSIONS (IN SITU)

CMP Total In-Situ UAR Total In-SituIsotope Fissions Fissions233U 3.974 x 108 f/].l9 ± 1.8% 2.666 x 108 ± 1.8%235U 2.704 x 108 ± 1.2% 1.772 x 108 ± 1.2%

~ 238U* 5.83 x 106 ± 1.7% 1.03 x 106 ± 3.4%239pu 2.560 x 108 ± 0.9% 1.717 x 108 ± 0.9%240pu 5.146 x 107 ± 1.5% 1.301 x 107 ± 3.4%241 pu 3.447 x 108 ± 2.7% 2.555 x 108 ± 2.7%

237Np 4.721 x 107± 1.5 1.047 x 107 ± 3.4%232Th 1.47 x 106 ± 2.6% 2.57 x 105 ± 4.5%

*Data from depleted uranium deposit.

48

---- --------------

The free-field results (Table XVI and XVII) will be used to compare with futureneutronics calculations. The core midplane free-field uncertainties lie inthe 1.4% to 2.7% range, while the upper location results have uncertaintiesfrom 1.4% to 4.2%. Spectral index comparison with calculations will be limitedaccordingly. It is possible that results from passive dosimeter measurementsin the IRT will resolve the 238U discrepancy and consequently reduce the finaluncertainties on all non-fissile results.

In conclusion, the primary purpose of the absolute fission chamber measurementswas achieved, and the results will be used in analysis of other IRT fissionrate measurements using radiometric techniques. Comparison of spectral indicesresults with neutronics calculations will be performed in the future, and otherIRT fission rate measurements may be used to reduce uncertainties in this com­parison.

VI. REFERENCES

1. "FFTF Reactor Characteri zati on Program," W/FFTF-C-760814~ HanfordEngineering Development Laboratory, February 1976.

2. "FFTF Reactor Characteri zation Experiments-Neutronic Experiments," HEDL­TC-1904, edited by J. A. Rawlins (to be pUblished).

3. J. A. Grundl, D. M. Gilliam, N. D. Dudey, R. J. Popek, "Measurement ofAbso.lute Fission Rates," Nuclear Technology, Vol 25, pp. 237-257,Febrr,uary 1975.

4. J. Van Audenhove, P. DeBievre, J. Pauwels, F. Peetermans, M. Gallet,A. Verbruggen, "The Preparation and Characterization of Reference FissionFoils," presented at World Conference of the International Nuclear TargetDevelopment Society, Munich, September 11-14, 1978.

5. J. L. Fuller, B. D. Zimmerman, D. M. Gilliam, J. A. Grundl, "Mockup Testingof the FFTF Reactor Characterization Program Absolute Fission ChamberSystem," HEDL-TC-1308, 1980.

49

APPENDIX A

DATA ACQUISITION SOFTWARE LISTING

A-l

t' .. ... • • p

C lIL.....0245

20. £H C PROGRA~1 1 t~lMlt·P I 10""'11/00 Rep UERSIOH20.02 0 CT20 .1£1 X FCHR< 7.127.. 12)j T fl PROGRAM &~~lM1H ~ It J I., !20.11 X F"TGL( 2 .. 1 ); X Fit:L( 4.d3)20.12 T Ii I t~lt'1IH' [llSPLA~tS At'41J STORES PULSE COUHTIHG DATA FROM AFC I~AAD~lARE THROUGH ORTEC IHe. SPECIAL IHTERFACE. U

20.18 T u MULTI~HfTl~OI~:K PULSE HEIGHT f1~~AL~(SIS IS ALSO PROUIOED. If

2lZf.30 T L. uCOut-ITIt~G I~lrERfJAL MUST BE LOHG ENOUGH FOR DATA OUTPUT (> 60r-Er."'" ') U Iv..,.:,:)" .t.20.40 0 3e20.74 ~ FT(3);X l A 3000jX FCHR«(J27}12)2fJ.76 T IINIMIH SET....UP COtfrIt'~UED: II .. I J 120.80 T I..! .. I'ST(4NDBV ~IHILE AI~AVS ZEROED"; F H==1., 198; S s< t4 )=020.82 T !20. B4 0 30.10

f' 20 .B6 T !..,N

21.36 T ! J f i A IIspECIFV ~4UMP..ER OF DETERMINATIOHS « 11). II .. DETER21.3S T ~;A uSPECIFY ROC P£f.=tL TINE IH SECOUOO: u, T21.40 T 1 jR uSET PRINT OUT COHTWi CYCLE MODE SWITCH TO ITlMED RECYCLE'U QZJ ,

21.42 T ~; A ··MANUALLY RESET ALL TIMERS II .. QQZ21.44 T t; A uSET T~lO ADC I S TO I COIHC I '~OOE III QQ2; T !21.46 T ~ .. I21 .47 A HspECIFV I RT I J THE FFTF TIME AT ST~lRT OF E~ERIHEHT (HRtl'~SC):u ~RT

21.48 T ~ ~ f ~ , j A "PRESS ... I RETURN' ... TO START AOC·S AT APPRX RT-3 SECTH8~ START COtJrrIHG HAP~WARE AT RT fi J Ql

21.50 }(Ql-eSTART)21.52J21.52s21.5221.52 x FAOC(lJ2J-T)iX 1~2000i~ FTGl(2J0)

22.08 S 0=1;5 H=l

F' u=1, 204.• S S( t~ )~S( t~ )-481(8<1)-0)27. 10~23.20J23.20S DATE':( D)=S( 1 )*1. E5"'S( 2)*11 E4+SC: 3)*1. E3+S( 4 )*100+S< 5)*10+S< 6)S CDE( 0 )=S( 9 )*10-l-oS< 9 ;.

22.10 X FX( -2 .. 013122.. 135)22.20 X FX(~2Je13070~26100a)22.25 X FX(-2~17Sb12)22 .27 S ~.RR;:;0

2"':J ~i7t 0 I?L... ·..,iU fr..

22.40 F H-l~2e4;S S(H)~FC~R(-l)22.50 0 TK

23.10........... it::'c.j, . a_I

23.20")3 -..........~. a £.G

23.24 S IHT(D)=S(10)*le0e+S(11)tl00+S(12)*10+S(13)23.26 S T 1M< [I )::;£.( 15 )%1 . E5+S( 16 )*1 . E4-t-S( 17 )*1000~S( 18 )t100+S< 19 )*10-4-$( 20)

23.2B S C(D}1)=s(22)*la£5+S(23)*1.E4+5(24)~1000+S(25)t108+S(26)t18+5(27)

23.30 S C( n.. 2 )=S( 29 )1:1 . E5+S( 30 )*1 . E4-l-S( 31 )*lBOO....S( 32 )tl00+S( 33 )*18·t-S(:.34::" ) .w

23.32 S C( 0 .. 3 )=S( 36 )*1. E5+S( 37 )=*1 .E4+S<. 38 )¥1000+S( 39 )*100+s( 40 )*10+S< 41)23.34 S C( OJ 4 )=S( 43 >*1 . E5+S( 44 )%1 . E4....S< 45 )%1 . f13+s( 46 )*100+S( 47 ):t10+S( 48)

23.35 S C<OJ5)=S(50)*1.E5+S(51 )*1.E4"'S(S2)*1.E3+s(53)*100+s(54)*10+S<55)23.38 S ex 0,6 )=5(57 )*1. E5+5( 5€t )t1 .E4+S( 59 ):~a .EJ+S< 60 )*180+S< 61 )*10+S( 62)

23 a 40 S C( D~ 7 )=$( 64 )t1 a E5+S( 65 )*1 .E4+S< 66 );t.l . E3'H5< G7 >*100+S( 6S)t10+s(69)23.42 S c( OJ B)~S( 74 :>* 1 . E5+~;( 7S ):1:1 .E4+S< 76)t1000<t·S( 77 >*100+S( 78 )t10+S( 79)

23.44 S C( 0".9 )=S( e1 )*1. E5+S( 82 )*1 . E4+S( 83 )*1000+s( 84 )*100+$( 85 )tlB+s( S6)23 . 46 S C( 0 J 10 )=5(88 )*1 . E5+S( 99 )*1 . E4+S( 90 )*1000+S( 91 )*100+s( 92)i:10....S< 93) .

~. ..... "" '" f,

;" t .. • ..

23 . 49 S C( 0 I 11 )=S( g5 )*1 . E5+::;( 96 )*1 . E4....$( 97 ):t.1000+S( ge )*10B+St: 99 )*10+S( 1€10)23.50 S C( (I, 12 )::.:S( 1a::: )*1 . E5+S( Ia3 )%1 .E"4"'S( 104 )*1000+$( 195 )t10B+S( IGg )*10+$(107)23.52 S C( 1:... 13~S( 109)*1.E.3+S( 110)tl.E4+$( 111 >*J.800·t-S{ 112)*100-4-S( 113'*1O+S( 114)23.54 S C(D.• 14):::S( 116)*1.E5+S( 117)*1.E4+s( 11&)*1.E3+S< 119)*100+S( 120)*1(:\+S( 121 )23.56 S c([) .• 15~t::;( 123)*1.E~+S( 124)*1.E4+s( 12S)*1000-f..S< 126)*100-J.S( 127)*1[H'S( 12E:) .23.~-8 S (:(D.. 16);:S( 130):t:l.E5"'S( 131 )*1.E4+S< 132):t:1ge0+S( 133)tl00+s( 134)*10+S( 135)~3.€e S C(O .. 17):=S( 137)tl.E5+S( 138)*1.E4·...S( 139)tl.E3-looS( 140)t100'''S( 141 '*10+S(142)23.62 S CCO.• 18)=s( 147)*1.E5i-S( 148)~1.E4+S(149)*1000+S( lS0)*100+s( 151 )*10+S( 152)23.64 S C(D.. 19)=-S( 154 )*1 .E5+S( 1~)tl .E4+S< 156)tl000+Sl. 15'i')*190+S< 158)*1~..I.e( 1t:'("01 -\

)::0 t:.1~ ....' ......... "

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24 . 10 G 25. 1024.12 X FC11R( 27~ 23); X 1A300B; ~ FCHR( 7.. 211 12); T I .. "DAT~ PARAMETERS t~E ~ tI

I f24.14 r ! .. '. DATE:", ~a. 0010ATE( 1 ).. •• EXPT. CODE: n J~3. 00.t n

AeCUM. HOISE COU"'TS~U.,"7.00 ..

u ~5I ..

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24.40 T ~:B.00;D 24.3424.42 T %8.00;0 24.3624. 43 ~ FCHJ« 7)j X lAUb0024.44 0 24.3824.46 T %8.00;0 24.3424.48 T %8.00;0 24.3624.49 X FCHr« 7); X l A 3000 .. T !24.52 I(n-DETfR)24.54~26.e2)26.0224 .54 C F I~1 J 205 j S S( 1 )~0

24.56 S D~+1;S H=l;G 22 ..25

25.10 I(O-2)24.12J24.20J25.1125.11 I(D-4)24.12J24.20~25.1225.12 1(0-6)24.12124.20125.1325.13 1(0-8)24. 12J24 .2~~J25.1425.14 I(O~10)24.12.,24.20J25.15

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25.16 I(D-14)24.1~~24.20~25.17

25.17 I(D-IG)24.1~~24.20~25.1S25.18 I(D~1~)24.12~24.20J25.1925.19 I(O-~0)24.12~24.20124.2e

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26.12 T ! .. ! J "STt.HOBV TO IHITIATFZ DAT~ STORAGE·1

26.14 x l A 15eeo;x FCHR(7J27,12)iX l A 100026.16 T uDATA STORf.iGE SEQU~HCE USIHG L T 17: II

26_18 T ~ I !.' ! ~f.:t "WHEN DISK Rl:AOY rl(PE tSTAf~TI II JQ526.23 1(Q5-eSTRRT)26.18.. 26.22J26.182&5 . 22 T , .• ~ , ~ , IIWHEH PROt'1PT J FILE: I APPEARS J R!=:SPOHD WITH DATA FILE: Htd1E

u.26.24 T ~J1"FORt1(4T IS 11rJNTH-DAt(-tR· ...CCOe:....iOETERMIHATIOHS; EG"J 9171<.011"II

f' 26.25 T ' .. ! J IIEXPERIJ1EHT CODE IS. U .. %3.0e.. COE( 1), II iOET'ERHIHf~TIO0'\ HS :;: II J DETER

26.26 T !26.27 L T 1726.3\1 L S26.:31 T RT26. :32 T DATl':( 0)26.34 T CDE(O)26 . :36 T I ~rr( D)26 .38 TTlt'K D)26.49 F J:;;l"O;F K~l.124;r C(JJK)26.42 T !26.44 L C26.42 r uRATE ~~TA STORED" .. !;,'26 .50 r ~.1 ~ .. ~ ; A U ARE THERE CORP.ESPONDI~4G HISTOGAAMS TO SAUE? ('(ES..~NO):

.. i'"ICJ I.J~

26.52 I(QG-0YES)26.76~26.54.. 26.7G26.54 T ! J , It .. lilt-ii-lEN PROt1p·r •FILE: I ~~EARS.. RESPO~t1 l4ITH HISTOGRAt1FILE

HAt-1E. u

26.56 T L, uFOR~1AT IS MQHTH-OAtt·.. •H t ....CODE; EG... 917HBl ..26.58 T !2" J"" '~r::t L Sb. ( \:.26.-l2 X FLD( 1,2048 )j L C:26. 74 T ~ J "HISTOGRAM [lATA SrOR~Ou ,f , ;}( 1#''06-0026 "76 X F'r( 3); X FT( 1 )26. ~~ T , .. IILII3RA~:Y LIST FRO~1 L T 1'(u .. !26.80 L L.26. $ret T ~ .• !." ·'PROGRf41 E1ID u

J !26.92 X lA50eOjX FT(3)j~ l A 200026.94 ~ ~TGL(2~1)

26.99 C!

27.10 C RESET EP~)R CORRECTION27.20 X l A l000;X t,:HR(7)iX 1~200;X FOHR(7);X l A 200;X FC~R(7);~ 1~~2B0JXFCHI;~ 7)j X 1~·2((}0i ~ FCHf.;:( 7)27 .30 S ERf<~~1

f 27.50 F·I=l,204;S s(I)=S(I~l)"-J 2' ~q r: ?3 "j1Zli & _ _ .., G. • e-IU

27 .80 T U ERR FLAG UP r.27.89 G 24.22

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b .'

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30.22 T IjA "SET I [JATE-COOE.... IHTERVAL....OEPOSIT. In OH Blt4CK DATA f1CJOULESu ,Q13

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( SHORT rtfrERUAL FLU>( MOH1 TOR SYSTEM II , Q1730.B9 R

31.02 C SUBROUTlHE TO SET UP 6 r~H8L DISPLAV31 .03 T I; A I' SET THlJt-1Blc!HEEL 11 TO I 00001 1

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31.12 X FORG(111)+FORG(2}1025)31.14 X F~~OS(500)

~ 31.20 X lAlr~0

& 31.22 X FctJR( 1J 1 )j X FCUR( 2J ?6E:)31.24 )C: ·l A l00031.26 X FTGL(2~1);X FlGL(3~1)

31.28 X lAl00031 .29 T ~; A It SET THtJl"1B~JHE:EL *1 T0 '09769 • II ~ 00831.30 X FTQ_(4~1)

31.40 X lAl00~3

31 . 42 X FCU~~ 1J 100 )+FCtJR( 2 .. 356 )31.90 C RETURN

96.10 F 1=0,512;X FPL(4*I~FB(0JI+1))

96.99 1'1

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97.209t~. 22~-1 3.!.~-~( ., ~'1-"1!- :i'~~ t . '\..:.4

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T ~.,'S LL~(CH-l)*2S6+20

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98.01 X FSTP(1~2)

98.Q2 X F2ER(1,204S)98.04 X FADC(1~2}-10e)

98.06 Q)::>I

\D 99~el L S HIMlf-bT fiE AU L:W AiT UtG 29.10 11 t;l CiL L

*

.. .,. " .,

APPENDIX B

DATA PRELIMINARY ANALYSIS SOFTWARE LISTING

B-1

" .. ., <

tL4C TIL-0245

II •• CHn

11 •• Q2

PROGRAf'1 'AFR I 11

60.10 C 2/18/81 UERSIOt~ OF AFR <DELETA13LE DETERt1IHATIOHS)60 . 11 X FCHR< 7 J 27 J 12)G3.12 T at

60.13 X FTGl<2J0)60. 14 T ~ .• ! J .. t AFR. . .' READS DlSV..ETTE-LT17 RCP-AFC COUtrr AUf) HISiOGRt..MOI~TA (ENTERED l)IA •Nlt~rN· OR f PTAPE I F(JRI1t4T). "60.16 T It THE COUNT DATA IS THEN REDUCED IN THE: CO~~UEHTIONAL HaS t~Nt-~ER (:tHD [I I SPLAVED FOR ~IA~~tJC(IF·V. II

60.18 T "rn:: HISTOGRtcf1 DRTA IS Af..SO DISPLAYED FO~ HARDCOPY. OEM TIME01'::.1(4 ENTERE))/Cfl1PIJTED lJIti GROUP 62. II

6fL 19 T It AFREXEC IS FIRST II~ SET OF C"HAINED ROUTIH£S.·'60.20 T !)!

OJ 60.22 A IISPI::Cl~r' HUf-taER OF fotETL~OPJ(S I~~ E)<PERIMEHT~ (FOR 11ONITOR ~ 2 .. FOR OTHER: 6):

60 .24 T·!.= A tI SPECIFY liONI TOR CNFI-fBEt{ t-.u.J1BE~ (6J 7 OR 8):.' Me60.29 T!) ! j A II IS PRINTER REt1iDlt( YES/HO)1'" ... Q169.30 I(Ql-0VES)60.2BJ60.32J60.2860.32 tt 11 IS DATA DISC IN LT17 AJ·I) ON-LINE?60.34 I(Q2-0YES)60~32J6a.35,60,32

60.35 r !J!/~I!

6fJ. 36 T 'I uDATLA WRIlTEH FOR lJl=f1. a*lJU u60.37 T I, "CHf.'di(;E LINE 64.21 IF DIFFEREHT OISCRI'"lt~TOR SETrIHGS USED"60.40 X 1110.3(:;00 .60.63 X FT(3);I(CH-2)60.62~6e.62J60.6463.62 S CC=4;G 60.7063.64 I(CH-6)6e.66~60.68,60.68

60.66 s CC~4jG 60.7060.68 S CC:::206e.70 S KC=CC+4;S U=0

61.10 T LJ t61.11 X FCHr«:7,27J 12)61.12 T nOATA READ SEQUEJlCE: n61 .1.4 T !., f .' ··CURREHT L1'"....17 OIRECTO~:V I II

61.15 L T 17JL L61 .17 TYPE I.. ~ .. uI4l~EH PRO~1PT •FILE:: I ttPPEARS IHPUT R~rrE DATA FILE ~~AMEti61 .18 T ! J I; R "SPECIFY HU~1BER OF DF::TERMINATIOHS IH DATA F'ILEJ 11,061.20 L A61 .21 H ·JIt161.22 fi DATE61.24 A CDE61.26 R IHT61.28 A TIM~1.30 F J=lJO;F K=lJ24jA R<J}K)61.32 L C(;1.34 T , J , J "R(:ifr:: DATA READ - STAHOB~' FOR SPECTRUM DISPl...AVu

If 61.36 0 Cj T "STAHOeti FOR SPECTRA OISPLAVu;O Tw 61.3.9 T.!." ~ , 1I(,.JfE)-~ PROI1PT I FI LE t APF'E~S I~~PIJT SPECTRA FILE tW4!u .. ~ } l

61.40 L A61 .42 X f-"1.R< 1~ 2048 ) j L C61.43 0 CT61.44 T fJul-iISTOGRPJtI DATA READ ..61.45 D 8561 .48 G t30. 1061.49 ~ ~TGL(2~e)jX FTGL(J,~)G1 .~)0 F 1=1.. D; F K~ I, 24 j S C( r .. KpR< I .. K)61.51 F I=l,tD;F K~1124;S R<I .. K)=0.061. ~~~2 -r ! ~ nDATA LIST AHtl ~~.7ILVSIS FOu..OltfS - STAHOBV"61.54 T II!'~

62.10 C OEADTIM~ DATA62.20 S T(3)=2.2462.21 S T(4):2.2462.22 S T(5)=1.78

.. . ,

':'-,."0 t J t ~

62.30 S T(6)~2.1S

62.31 S T(7)~2.1B

62.32 S T(8)~1.7B62.40 S T(11)~2.30

62~41 S T(12)=2.3062.42 S T(13)~1.7B62.~~ S r(14)~2.20

62.51 S T(15)=2.2062.52 S T(16)=1.74-- ~ "":l C· T" 1t". Ie ~ "".A.b~.6b ~ l ~J=~.~~

62.61 S T(20)~2.24

62.62 S T(21)=1.7762.~3 S T(22)~2.21

62.71 S T(23)~2.21

62.72 S T(24)~1.77

63.10 C DAT~ AHALYSIS63.12 S TIK~TIM/10.

OJ 63 -20 C [)I\JIDIHG FOR RATES1. 63.22 F ·J=1., OJ F K:::3, 8j S R< JJ K )=(.( J .. K)/Tll'1

63.24 F J=l,D;F K=11~16;S R(J~K)=C(JJK)/TIM63.26 t= J=l,[bF K~19J24;S R( J .. I()'=c(J.. K)/Tlt163.L~ X FTQ~(2,0)

63.30 C CORRECTING FOR DEAD TIME63.32 F J=l.,D;DO 7063 . 40 C Ctd._CS FfJR tllJE:PJ.)GES: MEAN63.42 F K=l ... KC; S Cf..il)( K )~.:0j S SA'.X K p0 JS QAl)( K)=0; S QBV< K)=0; S QRU< K)=e63.44 F J=1.~D;D 7163.50 F 1(=1 J KCi S CAU( K ):::C~I.J( K)/0; S SAlX f( )=SAU( K)/0; S GAll( K)ti\::QAlX K)/0; SQ8f,)( 1< )·~BIJ( 1< )/0 j S tU~l)( K ):::QRU( K)/063 . 70 C Ct.LCS FOR EXP. STD. OE:U.63.72 F K~l~KC;S Zl(K)~0;S 22<K)=0;S 23(K)~0

63.74 F J=lJO;O 7263.76 F K~l~KC;S Xl(K~FSQT(Zl(K)/(D-1»);S X2(K)=FSQT(22(K)/(D-l));S X3( K):::F'SQT( Z3< K)/( 0- 1))

63.78 C ~~It(K) ~ EXP. SID. DEU.63.80 C C~~CS FOR PRED. STO DEU.· SIGMA63.81 S L=463.82 F K~L~3JL+3;S SlG<K)=SAU(K)*<l./FSQT(CAU(K»)63. f.~3 F t<~.1 3 .. L+3j S S2G( I< )=FSQT< QAl)( K )*< QAU( l( )-) )/CAI.)( 1<)6.3.84 F K~L., 3.. L+3j S S3G( K)=FStli( ( (CAlX K)-( CAl)( K )*QRU( J(» )*( CAIJ( K )%rJRlJ( J() ) ) .....( C(4l)(: K);'·3 ) )63.85 8 L:::L+S63.86 I(L-CC)63.e2~b3,a2~63.9a6.3.90 C CALCS FOR S MEAN63.92 S RTD~FSQT(D)

63 .94 F K=1J KC; S M1( I( )=)<1 ( K::VRTO.; S tl2< K)=X2( K)/RTO; S M3< K)=X3( K)/RTD63.96 C ULCS FOR SIG MEAN .63.98 F K=l~KC;S G2M(K~S2G(K)/RTD;S G1M(K)=SlG(K)/RTD;S G3~K)=S3G(K)/

RTD

64 .02 C CALes FOR O£f.lD Tlt1E CORRECT1(Ii: 01TE:4 .e3 S XlJt--S

~ 64.04 S ·L~(J1 64.06 F K~} 3" L+3; S 01 T< K )=SAl)( K)/( C~J(K)/11M)

64 . 07 C CALCS For~ ElZ CORRECTI OH : El"2~4. 08 F' Kw;L.a 3~ L+3j S ETZ( K )=1 . 0'~l!J'"1*( QAt-X K ) ..... 1 .e)64.68 S L::.L+B64.70 I(L-CC)64.06~64.06,64.B964.89 L T 1864.90 L I AFRSl

70. 01 C DEAD TIt·1E SUBROUTIHE70.13 S L=470.12 r I<=L.I&J L+3j S S(..)" K-l )===R( .J" K...1 ,*< l·..R( J .. K-l )*T( K-l )*1.£-6); S S( J.t K)=R(.J.1K):t~(1+R(J.'()*T(K)*1.E-6)jS S(J.. K+l )=R(JJK+l )*( l+R<Jo'K+l )*T(K+l )*1.E-b)70.20 S L=L+970.30 I(L-CC>79.12,,70.12,,70.407f.L40 C R

;,-~• 'I; t 1

.. " t "

71.01 C AUERAGIHG SUBROUTIHE71 . 10 S L::.:471.20 F' I!.>=L .• 3 .. L+3j S CAl)( K )=CAl)( K} ..C( J .. K); 5 SAU< K):SAt..I( K )+S< JJI()j S QAlJ( K)~(;U:ll}( K)+~;( J.I l~-l )/$( J .. K ).1 E: OBl)( K)=QBl}( K)+S( J .. K+ 1)/$( JJ K)j S QRU( K )~Qj~I.)( K)+R( .J .• K+1 )/~:( J .. K)71.30 S L=L+B71.40 I(L-CC)71.20J71.20J71.5071.~~ R

72 ..al C E~. STn, DE\.J. SUBROUTI~E...,.- 1" ..... I 4i ~?. U .::. ... '::::.7"2,20 F K:;l .• 3~L+3j S El( l(pSAL'( K )-S( J.d(); S E2( K ):::QAlJ( K )-S( J .. K.... 1 )/S( JJ K);S E3< K ~BlJ( K )-S( J .. K+1 )/$( ~J". K)72. ~';10 F 1<='4_ .• 3) L+3j S 21( K ):=21 (K )+El( K)tEl( K)j S Z2< ~()~7.2( K)+E2( K)*E2( K); S

."1"-,,' K" .. ~2-,A' . l~ " i':'~ 1.1' "••,t.r.-""1( u' ...~.~( )~ ( )4·c )"'N:. v . 1'>. )

72 . 40 S Lo::l+872.!50 !(L-C(: )72. 20J 72. 20) 72.60

co 72.60 C RI

en

80,10 X 1~1000;X rT(3)JX l A l00080.12 ~ FCHR(7~27J12);X lA2B00BfJ.14 T uRt:iltl DATA FOR FIRST T~lO CHAHtELS~ II

00.15 S K~4

00.20 T !",80. 22 T 11 DETERI CLT CUT CGCTI'

CLB CUB CGCB

80.24 T ~J!8e .;-26 F .J=ls 0; T %3. a0J J) ~7. 80, R< J .. K-l )J R( J .. K)J R( JJ K+l )1 II II JR( JJ K+2), R(JJK+3),R(JJK+4)~!Be . :3eJ T L, f ; A If (-iRE: ~LL OE'TERf'1IHATI OHS TO BE ANAL\"'ZED (VESfHO): I' .. Ql80 .32 I F< Ql ....ff·(ES >'3 1 . 10, 8e . 40 J a 1 .1a80.40 T !~!J';G 61.49

81.10 X FTGL(2J0)

Bl.12 T ~ .. ~ ; A uHOW t1~~H~" OETERMIHATIOHS ARE TO BE DELETED FROM Af4ttL~(SIS ~Ie JND

Bl.20 T L. U n~PUT I~DICIES OF' DE:LETEO DETERM1HATIOHS: '1" !81 .30 F 1=: 1.. HO, T • I HPUT It~OEX HU~lBER: u .. I ; AU.' of OD( I )Bl.40 S L::::081.42 F I~l~DjD 8281 .50 S D-~""HD81.52 G 151.51

S2.1(t S ~1=e

a2 .20 ~~ ~~t-1""182.30 IF< M--HD >82. 40} 82.40182.5082.40 rF(I-on(M))82.20~B2.70.. a2.20B2.50 S L==L-l·182.60 F K~1 .. 24;S C<LJK)=R(I,K)32.70 C

! BS.01 C SUBROtffIH£ TO SET-UP 6 CHANNa [IISPlAVB5.02 X FT(,'L( 4 .. (3)85.34 X FOJR(1~1)+FCUR(2~768)85.06 X FTGL(2.. 0).iX Fl'GL(3s0)85 . 00 T !; ft .1 SET THtJqa~~HE:EL 1 TO ' 80ml' ... HI r RETURN n" QQAas.10 x FTGL( 2 .. 1)85.11 X FIJPOS(500);X FTGL(3Jl)i3~3. 12 T t; A "SET THUt1fj,JHEEL 1 ·ro I 09769 I ... HIT RETURN •• I QM85.14 C X FUPOS(500)85.16 C X .o;'lGL(3.,1 )a~5. t8 ~ FTGL( 4.1 1 )85.19 X 1.f~1.000g5 . ~~0 X FCUf~ 1 J 100 )+FCUR( 2 .. 356 )85.99 R

90.10 L S AFR;T uE A"ljT 11>( FTLIt'i(1550)··1,W Ail It*G 60.1Bli lil Coil L

*t."\ " , "

rd ""~ (. ... .

~1.J

C TIL-0245

SGC

n} Glt1<

It .. S3G(

SlB/SUB

II l 01T( K+3 )

11 , X3( K), .t

01M IHTERUAL: II J ~

'I ,~:6.00.. JIMDIM CODE: 11 .. %3. 0

.1 ~ G3~1( K), 11

SUBSGCT/SUTSLT/SUTsur

t: PROGRAl-1 AFRSl - 2/1a/81 Rep tJERSIOI'~S K:::::4X FT(3)X lA~000;X tCHR(7127J12);X l A 2000T '~"REACTOR TIME AT START OF DATA COLLECTIOHIT ,~UDlt·1 DttTE; u .t ~7. 00.1 OA1't.e II

6-'5.0165,0865.0965.1065.1565.16e.> eDt65. V:: T !} "CQfJtITIHG TII"IE (R~AL"'SECS): 1I .. ~7 .00, TIM.-·I5.00.. ItlT65,20: T ! .. uTOP CHI:--&-DEPOSIT. 11%7 . 00.. It ...' C( Do' K-3)65.22 T ! .. uBOTTD~1 (':HI....e.-DEPOSIT: ...t C( 0.. K....2)65.24 T !,! ..b5.26 T "DETERtB/SUBU~ f

~ 65.30 F ··J=l .. D; T %2.00.. J, II fa .. %6.02.. S( J... K) .. II "/~6.04JS( J .. K-l )/S( J .. K), It ..

co .. S(.J .. K+l )/S(JJK).... u .. ~6.0ZJS(J .. K+3).- .. uJ~6.04"S(JJK+~)/S<JsK+3) .. J1 ft .. S(J.. K+4)/S(J .. K+3),'6'5.34 T !J'J.!J!65 .38 T "1~1E(4N: It J %6 . 02 J S(lU( K) .. ~6 .04 s U U J QAV( K).. .. " J Q8U< K) .. I. II , %6 6 02 J S"·'It 1(+--'") ~6 ~4 It .. r.AU( K+3)" U M8l)( 1.1+-J:)11·.# .. r.... ..:a.). • .!(.J" J J~ ..... ..... J I~ ......;;)

&5 . 42 T ~ J ..S; I. J %3. 02.. u .. , Xl ( K) .. "5 .04, Ie II J XC( K) I I.

n Il.l-.} 0"5 X.1 ( It1-3 'j' ~5 04 II II ''!~( K+L')" .. )(.." K+3 ..).J. ' •••J • c:.. J t • 'I.' 1-.. J J. (.£.. -;) J J 1J'I"

65.46 T ! J uSIGt1A: II J~3.a2s II II JS1G(K).. %o.04 .. •1 t... S2G<K)J%5.84,"K),U ",%3.e2"SlG(K+3).,%5.04," It J S2G(K+3)," n J SJG<K+3)65.50 T !,IIS f;{EAf-~; '1 .. %5.04JM1(K),U .I JI'12(K).. 11 "Jt13(K)"II •• .. 111(K+3).• tl

II 'JtA:",>( K+3 )' II II H""'1( K+4!)) 1"1(_". ... J " oJ -. 'JF,e;; Ir"~JI T , •• CI G M ~.. ~~ ~4 U II r 1M.I K) II II G"='t,A", K ) II!:) ..........r'1' • J -..I !...3 '"I J .·oJ.lU" ,cU I·.... , J ~.I'. • ~

K+3)J .. n" G2J1( 1<-+3) ~ II II J G3t1( K+3)65.59 T ~,"OT COR:u,,%5 ..84,DIT(K).I U

65.62 T ~ J !65.63 D 77

65. g4 T u~LL RATES ABO~JE: CORRECTED O~LV FOR DEAOTlt1E MI" I

65.66 T ftDEAOTIMES lISED (USEe) -TOP~ TL:::;II .. :(3.02,T(Kao.ol),,·· TU_fl"T<I() .. ulGCt:: u

J i< K+ 1 )., I J •• . --ear ~ lL=u .. T( 1<+2).. II TU::ot uJ T(

K+3)" n TGC::U I T< K+4)65.67 X 1~400ejX FT(3)65.68 ~ lA2000iX FCHR(7,27J12)j~ l A 200965.69 T ! .. ,} IIFIHAL FISSION RAll2S FROM oerrA; II J %G. 00, DATE" ~3. 00J COE" ! JUDE:POSITS: It ._ :~7. 00.. C( D" K-3) .. II II) C( DJ 1(-2)65.lB 0 7B65.71 S CIR~ET2(K)*SAU(K)jS C2R=ETZ(K+3)*SALKK+3)65.72 T L· ~J!' L. L IfCORREC1'ED FJS$IOH RATE (l/SEC) - TOP~ ··J~7.a3.. CIR.. u +.....- ...' ~0 .. lJT65~74 T !J a• -- eOT1'OM: Jl .. ~7.03.. C2R.l11 +/_n." %0., ttB65.76 T t.I' J ~ .J 'IETZ CORRECTION - TOP: n .• :~5. ~4J ETZ( K)" U +/_u .. %0.. EIIM ..L, It ..... BOrrON: It J %5. (4) ETZ( 1<+3), II +/_11 J ~..0.1 E2Ut~

S5.78 T !.I' J t ~ "CORRECTIO~~S 1-.fOT APPLIED: Ii ~ !) It FRAGMENT SELF-ABSORBTIQHu J , :J 'J IJtPUR ITY FISSIOHSu J I J a. NEUTRON SCATTERIHG PEl~TURBATIO"~

Cf' SII .. ~ J II. FRAQ"IEf~T SCf:,TTERIHG"~ 65.80 T !~!~nOT ERROR OF +/- 0.2E-6 SEC IHCLUDED

65.81 T !" 1t,::r2 ERROR ALSO I~·ICLUCED·I65.82 I(U-0)65.90J65.88J65.9065.£B 0 7665.90 X lA2000iX FP(0J0J5);X FT(2)JX FT(3)

66.01 X l A 200@iX FCHR(7J27J12),X l A 200066.02 T ul.)f~r~lF='ICAT 101-1 FOR OA'Tr... 11.. %6.00 .. DATE.. ~~. 00" CDE.. I" U DEPOSITS : It .. %7.00 ~ C( 0 J 1<-3)J C( DJ K-;2 )66 a 10 T ~ J ~66.19 T "DETERt elT CUT CGCT ClB CUB CGCeu

66 .20 T ! J ,

66 _22 F J=:1 J0; T ~3. 00" JJ ~7. 00.. C( JI K-l ) .. C( J .. K) .. C( J .. K+l )" It " .. C( J .. K+2).1lC(J~K+3)JC(JJK+4)J ,66.24 X l A 40ee

...

'" f t .. :'II,

.... , .

67.01 C F~OTTIHG SOFTWARE67.12 S AA~120;S B~3e;S XC~60a6(~. 14 $ LL~0

67.15 X FF-< e.. ~C+10e*1 .2549J BB+310 )+rF'< lJ XC+100*1. 254~ .• BS+l~0)67. 16 C [)RAl~It·jG AXES67.18 X FP< a,d~IA", BB+310)67.20 ~ FP<1~AA~89)+FP(1)AA+320/B9)67.21 X FP(eJ~A+100*1.2549,Be~310)+FF(lJA~~100*1.2549~BB+120)67.22 x FP(0J~C~BB+31e)

67 . 24 X FF'( 1.- XC.' BE: »FP( 1, XC+320 J 88 )67 .26 S t-L=l+512*11 .• S ~tH=512"'512%U67 . 33 F N=f.JL.1 t·.H; D 7567.52 C DRAWING AXES DIUISIOHS67.54 F I=lJ4;D 67.5867 . 56 G 67. 64g7.SS x FP(0JAA+50*1.2549tIJBB)+FP(1~AA+50*1.2549*I/BB+le);G 67.69

If' 67.60 X FP< 0, XC+43%1 .2549+( 1--1 )*50*1 .2549/88); G 67. S2~ 67.62 X FP(lJXC+43*1.2549+(I-l)*50*1.2549/BB+10)

67.64 X FP(0)AAJBB+70)+~P(lJAA+10~BB+70)+FP(0JAA~BS+140)67 .66 X FP< 1.. A(-l+1 fJ ~ 88+ l40 )+FP( 0J XC, BB+70 )+FP( 1, XC+1 fj .. BB+70)b? GS :t. FP< 0J XC.. 88+140 )+FP( 1, XC+1BJ B~ 140 )+FP( 0J AA, B8+210)67.70 X FP( 1.,AA....10JB8+210)+FP(0.. XC"B8+210)+FP< 1J){C+l~l,BB+210)6'( .72 it: FP< 0.. AA" 8B+280 )+FP( 1 J AA.... 101 13B+280 )+FP( 0J XC.. B8+280 )+FP< 1J XC+10,8B+280)67.76 F I~1111;D 67.8067.78 G 6fLOO67 .B3 X FP< 0.1 AA-40 J ;250- I *2fH·BB ) j}~ FT( 2); G "'6'"'.82+.01 *167 <':t':) c- "'Z-t:'6'ft'4<I-f::i"A

• {.It:., '..1 K_ ....·.JIO-'9'· '"'~

67 1': ';/. 1" If I II• ij..::.t _

67.84 T "ou67.B5 T "Gil67 ,r..~ R

• l!::JO·.

67.87 R67.S8 T "ell

67.89......,. ~..,.,

bt ....~G'? .91tt:"-:> ~.~-Ul • ~'l..

6 '"'1' c ...t ~

T no··T uU"r "HitTilT·'T US"

Ga. (18 C LA8~LIHG OPDI~IATE68.10 F ]=1J5;0 68.1468.12 G 68.1868.14 X FP<0JXC-7ft.·BB-70+It70)jX FT(2); T "10 61 ;G 68.1668.16 >: FP( (1._ XC~B0., BB.....60+75tI )j g FT( 2)i T %2. 00J l.l:..·t+16-9« 18 C LABEL IHG ABSCI SSA68.28 F I=lJ6jD 69.2468.22 G 68.546B .24 X FP< 0.- --35+tlA+< 55*1 .2~A9*( 1-1 )).. 88-40); r.; 68.2668.26 S ZZ=50*I-50;G 68.2868.28 I(ZZ)G8.30J6S.30Jb8.32

co 68.30 S ZZ=1j X FT( 2 ) j Till II

~ 68.32 1(,ZZ-50 )68. 3f'" 68 . 34.J 68 .36..... 63.34 X FT(2)

68.36 1(2Z~100)6a.30J68.38J68.4068.38 X F"T< 2); T "100"68.40 I( 22-155::68.42" 6a. 42J 69.4468.42 X FT(2)68.44 !(ZZ....20e )(';8.301 69.461 68.4868.46 X FT(2);T 1120a ll

(8.49 I(ZZ-250)68.30~68.50,68.5068.50 X FT(2)68.52 X lA1.(j0a6B.54 ~ I=1~3;D 69.S868.58 S 22=100*I+200;G 68.606S.60 X FP(0IXC+110*1.2549*tI-l)~BB-40);G 68.6268,62 I(ZZ-250)68.67J68.64,68.6568.64 S ZZ=257;G 68.6768~65 1(22-500>68.67,,69.66168. 6S

Ie< !' • t "

,. " I ~. .. !I

68.66 S Zc~512~G 68.6768.67 X FT(2)JT %3.e0~Z2

~g. 6E~ S K::::!.:~·,"EU S U==U+168.80 I(K-CC)68.B2~68.e2)6a.90&9.82 X 1~5~0ejX ~r(3)

68.84 X FT(2);G 65.1068.86 X FTGL(2~1)68 ,~:t0 ~ FT< 2 )....oe. <:tl \.J FT( -~ )tx::; • ~. ".. '. .,;)-~ r.~ r~b. :'12 ~!

?5.01 C PLOnING $IJBROUTIHE75.1.0 1< Ft·1C:(.c( H) )75. 12.1 75.121 75.20~t::' 1"'" R.~ .J . l!. '.75.20 ~; ~t+"'512.w~j. 2;~ l( H....( 25f$+512*U) )75,30.. 75, Yj,( 75.4075 . :30 X r-:p( f1J ~·~A+At 1 .2549 J ( FLOt;( AlieA( H) )/2 .301259-LL )*70+B8 ) )75 .32 X FP< 1 J AA+< A-I )*1. 2549~ (FLOG( FMCtK H) )/2. 381259--LL)%70+SB))

~ 75.34 rl.;;:; 75.40 X FP< 0.. XC+( A....257)*1 .2549} ( FLOG( FHCA( N))/2 .30159-LL )*70+00) )

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76.02 C POf,18( LElJEL CALCULATION76.04 T !J!s~76.06 S ~RF~1.0009jS C~G.55E4

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APPENDIX C

NBS TRANSMITTALS ON RESULTS CALCULATIONS

C-l

UNITED STATES DEPARTMENT OF COMMERCENational Bureau of StandardsWashington, D.C. 20234

April 8, 1981

John A. RawlinsCore PhysicsHanford Engineering Development Co.Westinghouse Hanford CompanyRichland, WA 99352

Dea r John,

Enclosed are my 2nd level analysis work sheets for Experiment 5. In-Situ andFree-Field Fission Rates with estimated uncertainties (10) are given in Tables 2and 3. The work sheets which lead to these results are discussed briefly below.

Pages 5-1 through 5-5 list data from the program AFR along with weighted averagesfor the quantities Su and ETZ. The ETZ data from AFR was supplemented and/orreplaced by revised results from the recorded pulse-height distribution in afew cases where amplifier saturation noise obscured the scaler results. On pages5-2 and 5-5 the U-238 Etz's from AFR are replaced by 'best guess' values derivedfrom detailed analysis of the pulse height distributions. Additional specialtreatment of U-238 was also required to justify a lower error estimate for theresults from these heavy deposits. The basis for this special treatment is thatthe effective masses of the heavy U-238 deposits used in the FFTF experimentwere derived from fission-counting comparisons with standard deposits which aremuch lighter. To a large extent, the higher uncertainties in the ETZ and self­absorption corrections for the heavy deposits in the FFTF runs are cancelled outby almost identical corrections applied in the fission counting comparisons tothe standard deposits at NBS. The residual uncertainty then becomes primarilydependent on the thickness of the standard deposits rather than that of theworking deposits. Pages 5-5 through 5-8 show the deviation of the 'best guess l

ETZ's and the reduced error estimates.

In Table 1 are listed the In-Situ results prior to correction for fission inminor isotopic constituents. Table 1 includes error estimates for the followingfactors: statistics, dead-time, self-absorption, mass assay, and ETZ.

Pages MIC-l through MIC-14 give the derivation of the correction for fission inminor isotopic constituents and the derivation of the errors in these corrections.This correction-requires an iterative process in principle, but in fact theprocess converges in one step. The case of the normal uranium deposit againrequires special treatment. Here the special treatment is required because of thecorrelation with the U-235 fission rate.

C-2

- 2 -

In Table 2 the results from Table 1 are corrected for fission in minor isotopicconstituents and the complete In-Situ results and errors are given. In Table 3the Free-Field results are given, based on Table 2 and Core Physics Memo ofFebruary 24, 1981.

The results in Tables 2 and 3 are little changed from the 1st level analysis.The largest changes are due to the revised scattering calculations from L. L.Carter. These scattering calculations changed the power level normalizationuniformly for all the In-Situ results. The changes cancel out for the Free­Field results for the fissile isotopes. The revised ETI's for U-238 madechanges of up to 0.7% in the U-238 fission rates. The discrepancy in the U-238fission rates in the upper axial reflector was not resolved. I continue tobelieve that the possibility of unexpectedly large gradients in the fast neutronflux should be checked if possible. The revised Am-241/Pu-241 cross sectionratio gave a change of 1.44% in the CMP fission rate of Pu-24l. Overall, themany refinements that Fuller and I have labored over have produced littlechange in the results. The errors in the In-Situ results are within the goalaccuracy limits for all the CMP fission rates.

The 2nd level analysis for Experiments 8 and 10 should be ready very shortly.

Sincerely,

~ 1'V1 . ~;.)l:-Oavi d M. Gi 11 i amNuclear Radiation DivisionEnclosurescc: J. A. Grundl

E. D. tv1cGarryJ. L. Full ertJ s. CaSVJe 11".

C-3

J

U-233

U-235

U-238 (depleted)

U-238 (norm. uran.)

Pu-239 ..

Pu-240

Pu-241

Np-237

Th-232

TABLE 2.

EXP. 5: IN SITU FISSION RATES

CMPfissions/(s·~g.kw)

124.85+ 1. 55 %

84.94+ 0.86 %

1.834+ 1.45 %

1.827+1.72%

80.43+ 0.63 %

16.166+ 1.24 %

108.27+ 2.58 %

14.83+1.185;

0.461+ 2.63 %

C-4

UARfissions/(s·~g·kw)

83.74+ 1 .55 %

55.67+ 0.87 %

0.324+ 1.45 %

0.304+ 3.17 %

53.95+ 0.66 %

4.088+ 1.34 %

80.25+ 2.57 %

3.288+ 1.21 %

0.0808+ 2. 98 5~

U-233

U-235

TABLE 3.

Exp. 5: FREE-FIELD FISSION RATES

CMP

fissions/(s.~g.kw)

123.73+ 1. 96 %

84.18+ 1.48 %

UARfissions/(s.~g.kw)

81 .40+ 2.09 %

54.11+ 1. 65 %

U-238 (depleted) 1.865 0.335+ 1.88 % + 1.95 %

U-238 (norm. uran. ) 1.858 0.314+ 2.04 % + 3.43 %

Pu-239 79.71 52.44+ 1. 36 % + 1. 55 %

Pu-240 16.44 4.223+ 1.66 % + 1.87 %

Pu-241 107.30 78.00+ 2.85 % + 2.93 %

Np-237 15.08 3.397+ 1.61 % + 1.78 %

Th-232 0.469 0.0835+ 2.93 % + 3.25 %

C-5

J

.-

TABLE 1.

- IN SITU -PRIOR TO CORRECTION FOR FISSION IN MINOR ISOTOPES

U-238 28G-5-1U-235 Average of Above

CJI

O"l

Pri nci pa 1Isotope

U-233

U-235

U-235

Norm. U

Pu-239

DepositLabel

23K-02-8

25A-03-1

25A-03-2

28NC-5-1

49K-03-2F

CMPfissions/(s·vg· kw )+ combined errors

statistical err. %* self-abs. err. %tdead-time err. % mas~ err. %

ETZ err. %

124.86 + 1.55%0.09 0.350.05 1.5

0.1685.117 + 0.86%0.05 0.350.06 0.77

0.1484.851 + 0.86%0.10 0.350.04 0.77

O. 11-84.984 + 0.86%1.8483 + 1.45%0.05 0.350.07 1. 15

0.812.4355 + 1.27%0.04 0.350.09 0.95

0.7780.438 + 0.63%0.05 0.350.06 0.5

0.15

UARfission~(s.~g.kw) t combined errors

statistical err. %* self-abs. err. %tdead-time err. % mas~ err. %

ETZ . er'r. %

83.742 + 1.55%0.06 0.350.05 1.5

0.1255.742 + 0.87%0.11 0.350.03 0.77

0.1855.613 + 0.85%0.07 0.350.04 0.77

0.11

55.678 + 0.87%.33354 + 1.45%

0.07 0.350.07 1. 15

0.81.70275 + 1.27%

0.08 0.350.09 0.95

0.7753.953 + 0.66%0.1.1 0.350.03 0.5

0.22

("")I

-....J

TABLE 1. (continued)

PrincipalIsotope

Pu-240

Pu-241

Np-237

Th-232

DepositLabel

40L-2-3F

41K-03-1(L)

37K··05-1

02N-9

CNPfissions/(s.~g.kw) + combined errors

statistical err. %* self-abs. err. %tdead-time err. % mas, err. %

ETI err. %

17.257 + 1.24%0.06 0.350.07 0.8

0.8811 0.88 + 2. 56~£

0.08 0.350.04 2.5

0.44-.14.831 + 1.18%0.04 0.350.08 1.1

0.220.4608 + 2.50%0.095 1. 180.09 2.0

2.63

UARfissions/(s.~g.kw) + combined errors

statistical err. %* self-abs. err. %tdead-time err. % mas~ err. %

ETI err. %

4.8227 + 1.32%-0.06 0.350.04 0.8

0.9981 . 184 + 2.56%0.07 0.350.03 2.5

0.43-3.2883 +1.21%0.085 0.350.09 1.1

0.34-0.08083 + 2.87%0.16 1.180.07 2.0

2.98

* Includes statistical part of Ell error.~ Self Abs. Err = 25% of corr. or 0.35% whichever is larger lT Ell Err = 27% of correction \

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C-33

EX? 10

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101 f/g lOlTf/g(in situ) (in situ)

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Th·232 0.145 0.0254:t2.65% :!:3.00%

C-34

May 23, 1980

Dr. John RawlinsFFTF ProjectHanford Engineering Development Lab.Westinghouse Hanford CorporationRichland, WA 99352

Dear John:

UNITEO STATES OEPARTMENT OF COMMERCENational Bureau of StandardsWashington., D.C. 20234

- ,

-- --:

..

Jim Fuller suggested that I send you some documentation on the mass assay ofthe deposit 49K-4-1 which was used as a monitor during the neutron spectrometr,y ­tests at the FFTF in February. This information is summarized below.

Deposit Label: 49K-4-1

Backing: Platinum Disk, 0.75 in.DIA X 0.005 in. thick.

Deposit Geometry: 0.50 in.disk centered on backing

Uniformity of Thickness: Has not been measured. Color of deposit is uniform­across diameter, indicating uniformity within + 10%.

Batch Label and Isotopic Composition: Batch ORNL 277A

Isotope Atom Percent

239240241242244

239pU Alpha Activity:

,

99.978 + 0.0020.021 + 0.0020.0005 + 0.00030.0005 + 0.0003

< 0.0002

....( a)

(b)

1.082 X 106 sec- 1 by NBS Radioactivity Section

1.071 X 106 sec- 1 + 0.8% by NBS Neutron Field Standards'Group (Gilliam)

C-35

,sAlpha Acti vity Rq~io Reference Deposit:

4.500 + .27%

..

Fission Counting Ratio to Reference Deposit in Thermal Neutron Field:

4.492 + .7%

Published Reference Deposit (491-1-2) Mass:

104.8 pg Pu-239 + 1.0%

Derived Mass Values:

(1) Alpha activity (b) above and half-life value of 24,119 + 26 yr(Int. Jour. of App. Radiation and Isotopic, 29 No.8, Aug. 1978.):

466.8 pg Pu-239 + 1%

(2) Ratio to NBS Reference Deposit

471.6 pg Pu-239 + 1%

(The mass assay of the reference deposit is discussed in the 1975paper by Grundl, et al: "Measurements of Absolute Fission Rates,"Nucl Tech, .e, No.2, p. 237.

The second value of 471.6 pg Pu-239 + 1% is the currently recommended value.However, a revision of our reference-deposit mass assay is underway at thepresent time, and it looks probable that the reference deposit mass will berevised downward by 0.5% to 1.0%, which will bring the two results above intobetter agreement.

,

On another matter, the data processing for the February tests, I have a fewcomments to make. Jim Fuller and I have discussed the fission chamber results.I had only one minor reservation about the results: that the SL/SU ratio washigher than would be expected for a flow chamber. This deviation is caused(at least in part) by compression or-tne gas in the sealed chamber, but it ispossible that the SL/SU ratio was also increased by noise pick-up. Fuller ischecking to see how the peak/valley ratios from runs at the gamma pit compareto those from runs at the FTR. If we are to keep the full usefulness of theSL/SU ratio as a noise diagnostic, then we are going to have to find a way toaccount for the influence of chamber filling pressure. We are working on theproblem jointly.

Sincerely, ..

~ "l" ..; ~ ,"--' .' : .~ ~~\ \\\. ,~,-l, ~

D. M. Gilliam .Center for Radiation ResearchNeutron Field Standards

2C-36

, .

Pu·239

Reference Deposit Assay

Techniques Employed:. (LASL) .

(1) IDMS (Isotope Dilution Mass Spectrometry)(2) Absolute alpha countng with specific activity from

(a) literature half-life .' .(b) quantitative depositon .

Accuracy: ± 0.4'

Working Deposit Assa~

Comparison to Reference Deposit by: ~~~ Alpha countingFission counting

Estimated Errors .... : 0.3% to :l: 0.4% in comparisons. Assessed errorsslightly larger than initial estimate if fission and alpha comparisonswere not consistent within estimated uncertainty.

U-235

Reference Deposit Ass~y

Techniques: Same as for Pu·239 (except 10MS @NBS)

Accur8cy: ± 0.5%

Working Deposit Assay

Comparison to Reference Deposit: (.21) Fission counting (~ 0.60%)() Alpha counting (± 1~451)

(given low weighting)

Pu·240

Working Deposit Assay

1.) IOMS (CBNM Geel) t 0.9% .2.) Absolute alpha activity with literature halfI-life ±

(agreement better than =0.11.) .

C-37

0.8%

, ,," '.:.. '

Np-237

Reference Deposit Assay

Technique: Absolute alpha counting with specific activity by(1) Literature half·life . ,(2) Quantitative deposition· .

Accuracy: :f: 1.0%

Working, Deposit Assfty

Comparison to Reference Deposit: (1) Alpha countng (t 0.3%) ..(2) Fission Counting in ISNF ( 0.3%)

Agreement of fission &alpha ratios:0.44%

Natural Uranium

Reference Deposit Assay

Techniques: (21) IOMS (NBS)() Fission comparison to 235u Ref. Dep. with thermal neutrons

+ 28/25 isotope ratio(3) Absolute alpha counting with specific activity by

quantitative deposition

Accuracy: :f: 0.7% [(3) given low weight]

Working Deposit AsslY

Comparison to Ref. Dep by thermal-neutron induced fission counting:: 0.64%

Depleted Uranium

Reference Deposit Assay

Techniques: (21) IOMS (NBS)() Fission ratio to Nat. Uran. Ref. Dep in Cf-252 Neutron field(3) Absolute alpha activity with specific activity from literature

half~life '

Accuracy: ± 1.0%

Working Deposit Assay

Comparison to Reference Deposit in Inter~ediate-Energy Standard NeutronField (ISNF): ± 0.74%

C-38

U·233

Reference Deposit Assay

Techniques: (1) Absolute alpha counting using literature half-lifefor specific activity

(2) Thermal.neutron induced fission ratio to Pu-239 deposit(a) maxwell iam spectrum ,.! ,.,

(b) monoenergetic neutrons with 3S milli-el~ctron voltenergy I

(1) and (2) differed by 0.84%

Accuracy: ± 1.5%

Working Deposit Assay

Comparison to Reference Deposit: (1) Thermal ..neutron induced fissioncounting (± 0.311)

(2) Alpha counting (± 0.5%)

(I) and (2) differed by 0.23%

Accuracy: ± 0.3%

Th-232

Reference Deposit Assay

Technique: Absolute alpha counting using 'literature half-life for specificactivity

Accuracy: ± t ~

Working Deposit Assay

Comparisons to Reference Deposit: Alpha countingFissio~ counting in IS~F

Accuracy: ± ~

C-39

Working Deposit Assay

Techniques: (1)

'. .

Pu-241

Absolute alpha counting of Am-241 build-up overfive month period, beginning 22 monttls after!separation, I

(2) Thermal-neutron induced fission comparison to, Pu-239deposit in a 35~eV monoenergetic beam

(1) and (2) differed by 2.4%Equally weighted average used. Estimated accuracy. ~ 2.5% .

Choice of Geel - CBNM laboratory: No U.S. laboratory was equ;ped tol make double­-rotated vacuum evaporati on deposi1t ions. (LASLused to have this capability. but: not now - atleast, not for outside purposes.)

Choice of Fluoride as Chemical Form: Has lower sublimation temperature thanoxides. Fluorides tend to deposit assingle molecules while oxide moleculestend to condense into clumps as theystream from the crucible to the backing.For fluorides it is not necessary to heatthe backings, and the single-moleculesadhere better than clumps.

C-40

APPENDIX 0

HEDL-CALCULATED FREE-FIELD SCATTERING CORRECTIONS

0-1

From:Phone:Date:Subject:

To:

Radiation and Shield Analysis Hanford Engineering Development Laboratory6-5193 and 6-0153 W/B-47February 18, 1981PERTURBATION IN FISSION CHAMBER MEASUREMENTSDUE TO NEUTRON SCATTERING WITHIN CHAMBER

cc: RA BennettWL BunchJW Daughtry

L RS McBeathFS MoorePA Ombre11 aroLLC - File/LBSAS - File/LB

Ref: (1) OSI, JA Rawlins to LL Carter, November 21, 1980.(2) LL Carter and ED Cashwell, IIPartiCle Transport Simulation Hith The

Monte Carlo Method,1I TID-26607, ERDA Critical Review Series, U. S.Energy Research and Development Administration, Technical InformationCenter, Oak Ridge, TN (1975).

Monte Carlo calculations have been made to determine fission rate changesdue to the perturbation caused by the presence of the fission chamber attwo axial locations within the IRT. The axial locations considered werecore midplane and 80 cm below core midplane with the pristine spectraobtained from Ref. 1. Fission rates were calculated for 238U and 239PU.

...

The calculations summarized in TabJe 1 are for infinitely dilute concen­trations of 238U and 239pU, and hence, do not include self-shielding dueto the fissionable materials. Difficulties were experienced in obtaininggood precision in the calculations so that the ratios given in Table 1are only accurate to about one percent (one standard deviation). Thelargest statistical errors resulted for the calculation of the 239pUfission rate with the softer spectrum, even though more computer timewas expended on this case. For this case more than 75% of the fissionsoccur in the resonance range below 1 keY, ~nd the random walk integrationover the resonances increases the statistical error substantially.

The source was biased (Ref. 2) in both energy and angle to improve theprecision of the Monte Carlo calculations. To obtain greater precisionone would need to make longe~ computer runs or possibly utilize moresophisticated biasing techniques.

D-2Westinghouse Hanford Company I A subsidIary of Westinghouse Electric Corp. I Operating the Hanford EngIneering Dev"lopment Laboratory fo< the US DOE

J. A. RawlinsPage 2

The computer drawn model of the fission chamber is shown in Figure 1. Thematerials utilized for the main portion of the chamber are shown in theexpanded view of Figure 2. Both materials and dimensions were utilizedas specified in Reference 1.

Neutrons were started uniformly on the spherical surface (radius=3.84 cm)shown in Figure 1 with a cosine inward distribution. The source strength 'was normalized to yield a unit flux everywhere within the sphere for thepristine configuration with detector absent.

ENOF/B-IV neutron cross sections were utilized in the calculations.

L. 1:. Ca rte r

llr

Attachments: Table 1Fi gures 1 and 2

0-3

,la. Jck;kS. A. Schenter

Table 1

FISSION RATES FOR UNIT EXTERNAL FLUX

Fission Rate (fissions/g)

•

Core Midplane SpectrumDetector IncludedDetector MaterialsTreated as Zero Density

Ratio

80 cm Below Core MidplaneDetector IncludedDetector MaterialsTreated as Zero DensityRatio

9.7llxlO- S (O.91%)*

9.883xlO- S (0.60%)

0.983 (1 •1%)

8.719x10- 6 (O.79%)0.968 (1.3%)

4.511xlO- 3 (O.62%)

1 .009 (1. 2% )

2.002xlO- 2 (1.2%)

1.945X10- 2 (O.79%)

1.029 (1.4%)

*One standard deviation statistical error in theMonte Carlo calculation.

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