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UNCLASSIFIED

Materials HandbookMaterials Handbook

• Started for the APT project• Continued in AAA• Now accepted as the GenIV handbook

Stuart Maloy (LANL)Phil Rittenhouse (ORNL, ret)

UNCLASSIFIED

UNCLASSIFIED

Rev. 4 of the Materials Handbook will be ready for distributionin October 2003

Rev. 4 of the Materials Handbook will be ready for distributionin October 2003

Table of ContentsVolume 1

1. Introduction 2. Inconel 718 3. 316L SS 4. 6061-T6 Al 5. 316L/6061 Joint 6. Lead 7. Tungsten 8. Niobium 9. Titanium 10. Graphite 11. Alumina 12. (Placeholder) Fiber-Optic Materials 13. (Placeholder) Accelerator Component Materials 14. Tritium System Materials 15. Coolants/Fluids 16. 304L SS 17. (Placeholder) 1040 Carbon Steel 18. (Placeholder) 430 Ferritic Steel

19. NEW in Rev. 3 Design Properties of Mod 9Cr-1Mo (T91)

20. (New in Rev. 4) Design Properties of HT-9 and Russian Ferritic-Martensitic Steels

21. (New in Rev. 4) Design Properties of Tantalum

22. NEW in Rev. 3 Design Properties of Lead-Bismuth Eutectic

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Recent Handbook ActivitiesRecent Handbook Activities

Review and final revisions to Chapter 21 on Tantalum were Completed• Original draft of the chapter was prepared

by Hans Ullmaier of the ESS Project at Forschungszentrum Juelich

Handbook Chapter 18 on HT9 ferritic/martensitic stainless steel was drafted and reviewed• First complete draft prepared by the

Handbook Coordinator

• Based on a first partial draft prepared by Todd Allen on ANL

• Chapter includes selected information on Russian ferritic/martensitic steels of similar composition to HT9.

• Russian steels have higher Si content to provide increased resistance to attack in Pb-Bi eutectic.

Both chapters will be ready forinclusion in Revision 4 on the Materials Handbook in the Fall

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MCNPX DevelopmentsMCNPX Developments

Laurie Waters

High Power Targetry for Future Accelerators

September 11, 2003

UNCLASSIFIED

UNCLASSIFIED

MCNPX 2.5.d released August, 2003MCNPX 2.5.d released August, 2003

John S. Hendricks, Gregg W. McKinney, Laurie S. Waters, TeresaL. Roberts, Harry W. Egdorf, Holly R. Trellue, Joshua P. Finch,

Nate Carstens, LANLFranz X. Gallmeier, ORNL

Jean-Christophe David - CEA-SaclayWilliam B. Hamilton, HQC Professional Services

Julian Lebenhaft, Paul Scherrer Institute

SponsorsEric J. Pitcher, Doublas R. Mayo, Martyn T. Swinhoe,

Stephen J. Tobin, Thomas Prettyman- LANL

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MCNPX Code AcceptancePhotons Electrons Neutrons Protons Photonuclear Other single Light Ions Heavy Ions

µ Π Κ ν, etc d t s a

1 TeV Quantum Models

1 GeV ModelsINC, Pre-equilibrium, Evaporation modelsTables or Models

1 MeV

TablesIn progress

1 keV

1 eV

Thermal

Mixing

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MCNPX Events During Past YearMCNPX Events During Past Year

• Version 2.5.b released Nov 26, 2002• Version 2.5.c released Apr 3, 2003• Version 2.5.d released Aug, 2003• 1113 beta testers, 250 institutions (28 users in progress)• 5-day Classes

– SCK-CEN, 20 students– Orlando, 15 students– Santa Fe Community College, 23 students– MD Anderson Cancer Center, 24 students– Santa Fe Community College, 16 students

• 2 summer students, – Nate Carstens- MIT (speedup of parallel KCODE Calcs.)– Josh Finch- Purdue (new test problems)

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FundingFunding

• AFCI• Mars Odyssey

– Water on Mars, July 2002 issue of Science, Distinguished Performance Award just announced

• Threat Reduction– Groundwork CINDER implementation work for delayed

neutrons in active interrogation– Maritime cargo container project– Nonproliferation/Safeguards - various projects

• Heavy Ions– Rare Isotope Accelerator, NASA, AFCI fuels

• Isotope Production Facility

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Code Applications as of 8/25/03Code Applications as of 8/25/03

• Medical 70 groups 201 people• Space reactors, cosmics 54 groups 115 people• Fuel Cycles 50 groups 140 people• Threat Reduction 47 groups 124 people• ADS 45 groups 185 people• Accelerator HP 33 groups 101 people• Applied Physics* 31 groups 83 people• Neutron scattering 16 groups 81 people• Code development 18 groups 28 people• Physics models, data eval. 9 groups 18 people• Nuclear, HE, Astrophysics 8 groups 56 people

* Radiography, oil well logging, irradiation facilities, isotope production, detector development, environmental, high density energy storage

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MCNP4C3 FeaturesMCNP4C3 Features

• Macrobody geometry• Superimposed mesh weight windows• Interactive geometry plotting• Perturbations• Unresolved resonances• Photonuclear reactions• Delayed neutrons• ENDF/B-VI physics• PC enhancements• ITS3.0 electrons• Parallelization

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MCNPX 2.4.0 RSICC Release - Sept 2002MCNPX 2.4.0 RSICC Release - Sept 2002

• F90 modularity and dynamic memory allocation (GWM)• Distributed memory mulitprocessing for all energies (GWM)• Repeated structures source path improvement (LLC/JSH)• Default dose functions (LSW/JSH)• Light ion recoil (JSH)• Enhanced color geometry plots (GWM/JSH)• Photonuclear and proton cross section plots (JSH)• Photonuclear and proton reaction multipliers with FM cards (JSH)• Logarithmic interpolation on input cards (10log) (JSH)• Specify cosine bins in degrees (JSH)• Cosine bin specification for F2 flux tallies (JSH)• Pause command for tally and cross-section plots (JSH)

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Photonuclear Cross Section PlottingPhotonuclear Cross Section Plotting

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MCNPX 2.5.b FeaturesMCNPX 2.5.b Features

• CEM2k physics models (SGM, AJS, FXG,JSH)• Mix and Match solution (JSH)

– Isotope Mixing for different particles– Energy Matching between libraries and models

• Positrons enabled as source particle on SDEF card (HGH)• Spontaneous fission (par=sf on SDEF card) (JSH)

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Mix and Match - Energy MatchingMix and Match - Energy Matching

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MCNPX 2.5.c FeaturesMCNPX 2.5.c Features

• MPI Multiprocessing (JL/GWM)• i,j,k lattice indexing in geometry plots (JSH)• Enable weight window generator in physics model region

(FXG,JSH)• Enable exponential transform in physics model region (FXG,JSH)• Extend neutron model physics below 20 MeV (JSH)• 3-He coincidence detector modeling (HGH/JSH)• F90 Autoconfiguration (TLR)

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i,j,k Plotting on Lattice Cellsi,j,k Plotting on Lattice Cells

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MCNPX 2.5.d FeaturesMCNPX 2.5.d Features

• INCL/ALBA physics models (JCD/JSH)• Lattice tally speedup for rectangular meshes (GWM)• Multiple particles on SDEF cards (JSH)

– Can depend on other variables– Normalization

• Auxiliary input files, ‘READ’ card (JSH)• Geometry plot of weight-window-generator superimposed mesh (JSH)• Pulse-height light tally with anticoincidence, FT8 PHL (GWM)• Coincidence capture tally and PTRAC file, FT8 CAP

(MTS/SJT/DRM/JSH)• Residual Nuclei Tally, FT8 RES (JSH)• Inline generation of double differential cross sections and residuals

(JSH)

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Secondary Particle PlottingSecondary Particle Plotting

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Future WorkFuture Work• User support and testing• Error Analysis

– Completion of perturbation techniques in model region– Data covariance analysis

• Criticality– Externally driven source– Improve stability of eigenfunctions– Improve parallel processing for KCODE calculations

• Transmutation– Inlining of CINDER’90 for transmutation work– Monteburns and Cinder are about to go up on the beta test page

• Variance Reduction– Variance reduction for pulse-height tallies– Detectors and DXTRAN for all neutral particles at all energy ranges– Secondary particle angle biasing for isotropic distributions– Next-event-estimators for charged particles

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Future WorkFuture Work• Physics improvements

– Heavy ion and low energy transport improvements for fuels work– Upgrade physics models as they become available, e.g., LAQGSM/CEM,

ISABEL• Miscellaneous code features

– Plotting of physics model total and absorption cross sections– Lattice tally contour plotting– Interactive tally and cross section plotting– CAD link– Integration of HTAPE tallies directly into MCNPX– Parabolic beam source– Addition of MCNP5 features

• Software Engineering– INTEL and 64 bit computer support– Improvements in autoconfiguration system

• RSICC Release in December 2003

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TRACE Code Development and ApplicationsTRACE Code Development and Applications

High Power Targetry for Future AcceleratorsSeptember 11, 2003

ByJ. Elson and J. Lin

Nuclear Design and Risk Analysis Group (D-5)

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OutlineOutline

• TRACE Overview– Roles– Sponsors– History– TRACE Modernization– Code Characteristics and Capabilities– Code Qualification and Software Validation

• TRACE Applications for Accelerator Systems– DELTA-Loop Performance Benchmarks– LANSCE-1L Test Facility Safety Studies

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D-5 RolesD-5 Roles

• Transient Reactor Analysis Computational Engine (TRACE) software development

• Software validation• Software applications• Consulting and training services

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SponsorsSponsors

• US Nuclear Regulatory Commission (NRC)– Office of Nuclear Reactor Research (RES) -

Primary Sponsor• Division of Systems Research; Reactor and Plant Systems Branch

– Office of Nuclear Reactor Regulation (NRR) -Secondary Sponsor

• Knolls Atomic Power Laboratory (KAPL)

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HistoryHistory

• TRACE under continuous development for the U. S. Nuclear Regulatory Commission (NRC) since early 1970

• TRACE continues to evolve with increasing understanding of complex two-phase, multi-component fluid phenomenology

• NRC sponsored multiple codes for 20 years• NRC has now selected TRACE as the sole platform

for future development• Ambitious multi-institution development program

underway

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TRACE Development EnvironmentTRACE Development Environment

NOW(1997 to Present)

THEN(1970’s to 1997)

ISL

PurdueUniv

PennState

LANL

NRCIntegration

LANLDevelopment

and Integration

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TRACE Modernization EffortTRACE Modernization Effort

• Modernized a legacy code...– Updated non-ANSI-standard code to Fortran 95– Added new component models

• Added BWR component models to what was previously a PWR code

• Added RELAP5 components (e.g., single-junction component)

– Enhanced numerical solution algorithms– Added multi-dimensional kinetics (PARCS code)– Added new material properties (Na, He, Pb-Bi, other)– Updated the Validation Test Matrix

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TRACE Modernization EffortTRACE Modernization Effort

• Modernized code is highly modular and object-oriented

– Order of magnitude easier to maintain and modify• Liquid metal fluid properties added to TRAC-M and tested

within 2 staff-weeks• Prior versions of code may have required several staff-

months for the same task– Enhanced parallelization

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TRACE Characteristics and CapabilitiesTRACE Characteristics and Capabilities

• Modular, object-oriented F95 standard coding• Generalized two-phase thermal-hydraulic

modeling capability (plants & test facilities)– Two-fluid model - 6 equation model– Multi-dimensional VESSEL component– All other components modeled in one dimension

• Pumps, pipes, valves, etc.– Primary, secondary, and containment may be simulated

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TRACE Characteristics and CapabilitiesTRACE Characteristics and Capabilities

• Multiple fluid modeling capability– Primary and secondary loops can be modeled with

different working fluids– Available fluid models include H2O, D2O, He, Pb-Bi, Na,

N2, air, oil, and RELAP5 H2O• Non-condensable gas model (H2, air, etc.)• Trace species tracking capability

– Track trace gas and/or liquid species– Includes solubility models for trace species

• Fluid volumetric heating and fluid decay heat models

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TRACE Characteristics and CapabilitiesTRACE Characteristics and Capabilities

• Single-phase and multi-phase heat transfer models

– Includes liquid metal heat transfer models• Multi-dimensional heat structure models

– Cylindrical, rectangular, and spherical heat structures– Multiple materials

• Generalized radiation heat transfer modeling

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TRACE Characteristics and CapabilitiesTRACE Characteristics and Capabilities

• PWR and BWR capability within the same code version

• Enhanced BWR fuel assembly models– Partial length fuel rods– Water rods and channels with diameters and geometry

different from fuel rods• Point and multi-dimensional kinetics

– PARCS code allows for multi-dimensional, transient coupling

– Point kinetics model also available

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TRACE Characteristics and CapabilitiesTRACE Characteristics and Capabilities

• Multiple processor capability• External component model

– Allows different parts of a model to run on different processors

– Can be used to couple TRACE to other computer codes or models (e.g. CFD, etc.)

• TRACE coupled to HMS CFD code with one staff-week effort (high-level waste tanks)

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TRACE Characteristics and CapabilitiesTRACE Characteristics and Capabilities

• Runs on a variety of platforms• Platform-independent graphics and restart files• Input can be generated by GUI front-end (SNAP)

– SNAP takes basic plant geometric and materials data and generates input files for TRACE

– SNAP can read RELAP5 input decks and generate TRACE input models

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Code Qualification and Software Validation

Code Qualification and Software Validation

• TRACE code has been validated to ensure that all code features, models, and integrated calculation capabilities are tested

• Large data base of assessments against LWR actual plant data and experiments

– Separate effects tests, component effects tests, integral effects tests, and other standard tests

• TRACE Validation Test Matrix includes ~1000 test problems

• TRACE adheres to NRC Software Quality Assurance requirements

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Code Qualification OverviewCode Qualification OverviewQu a lified TRA C

Cod e

Re qu ire men ts D efin it ion , Design , a n d I mp lemen tation1. Field E qua tion s 2. C losu re Relat ion s 3. C omp onen t m od els 4. Sp ecia l Mod els 5. N u me rics

Ve rifica t ion

Valid ation usin g

Se para te E ffects Te sts

Va lid at ion usin g

I n teg ral E ffect Te sts

Docu men tatio nDe scrip t ion

Requ irem en t s Do cu m en ts Ve rifica t ion an d Va lid at ion P lan Sof tw ar e Project P lan Sof tw ar e De sign Docu men tation Qu alific at ion Te st P lan a n d P roced ures Ac cep t an ce Te st Pla n an d Pro ced u res

Focus on C losu re Relat ion sh ip s (e .g., C orre ct Eq uations U sed ) Fe w P h en omen a/ P rocesses Simple Geomet ry C on tro lled Bou n dary Con d it io ns

In tegr ated Cod e Be h av ior • Fie ld E quat ions • Closu re Rela t ion s • Comp on en t Mod els • N u me rics • Sp ecia l Mo d els Sc enar io Ap p lica bility Sc alin g to P lan t Con d it ion s

Qu alific at ion Te st Plan Qu alific at ion Te st Pr oced u res Qu alific at ion Te st Re p ort Ac cep t an ce Tes t Pla n Ac cep t an ce Tes t Proced u res Ac cep t an ce Rep ort Use r Do cu m en ta tion

Sp ecif ied D esign Fea tu res / Fu n ct io ns Eq u ilib riu m Prob lems C once p t P roblem s A n alyt ical Proble ms N u me rical Met h od Tes ts

A n alyz e Re qu ire men ts D evelo p Pre limin ary Design D evelo p D etaile d D esign D evelo p C ode U nits In spec t ion s Re v iew s

Fig. 2-1. C ode Qua lifica tion Ove rview *

* For ad d it ion al in for mat ion se e N U REG / BR-0167, "Softw are Q u ali ty Assu ran ce P rogra m an d Gu id el ines, " US N RC (Fe bru a ry 1993)

Va lid a tion us in g

O ther Stan d ard s

Rev iew s Au d its Pee r In sp ec tions In f orma l Tests

Verif icat ion an d Valid at ion Pla n Rev ie w an d Au d it P acka ges P eer In sp ectio n Pa ckag es I n for mal Test Plan s, P roced u res, Resu lts

Qua

lific

atio

n T

estin

g*

Val

idat

ion

Test

Mat

rix

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Software ValidationSoftware Validation

PIRT Summary

Process Phenomenon Rank

blow- down

slow depress

Crit Flow Flashing . . . Crit Flow Decay Heat . .

17 15 2 2

PIRT Library • WEC 4-Loop LBLOCA • AP600 LBLOCA • B&W SBLOCA • AP600 SBLOCA • AP600 MSLB • SBWR MSLB • SBWR bottom drain line LOCA • SBWR GDCS line LOCA • AP600 SGTR • Production Reactor DEGB

Acceptance Test

Matrix

TRAC Models

Global

ClosureInterface Area Interface Drag Interface Heat Transfer Wall-Liquid HT Wall-Vapor HT Wall-Liquid Drag Wall-Vapor Drag

Field Equations Components Neutronics Numerics

Information Sources • TRAC Theory Manual • AP600 LBLOCA Developmental Assessment Plan • TRAC PF1/MOD2 AdequacyAssessment: Closure and Special Models

Selected Tests

Experimental Data and Other Test Problems

Features Tests Equilibrium Problems Concept Problems Analytical Problems Numerical Method Tests Fundamental SETs Other SETs IETs Plant Events

Information Sources • OECD SETs Matrix • OECD IETs Matrix • CATHARE Test Matrix • RELAP5 Test Matrix • TRAC Test Matrix • Development History

Selection Criteria for SETs and IETs • Quality of Data • Availability of Data • Range of Data • Nature of Data (Fundamental Desired) • Availability of Existing TRAC Deck

Fig. 2-3. Information sources supporting creation of the Validation Test Matrix.

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TRACE ApplicationsTRACE Applications

• Analysis applications enhance understanding of key processes

– Accidents and transients– Licensees' calculations (auditing)– Test planning– Test assessment– Design performance

• Applications have included PWRs, BWRs, heavy-water reactors, experimental facilities, and accelerator facilities

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DELTA Loop Facility(Liquid Lead-Bismuth Materials Test Loop)

DELTA Loop Facility(Liquid Lead-Bismuth Materials Test Loop)

Heated Section

Sump Tank& Pump

RecuperatorLBE-to-LBE-to-Water

Heat ExchangerTube Side

Shell Side

PumpBypass Line

Melt Tank

Test Section

RecuperatorBypass Line

3.8 m

O2 Injection

• 60kW Heat Input• 58 gpm pump flow• Recuperator• LBE-to-LBE-to-H2O Heat

Exchanger• 2” 316SS Piping • 1” Piping in Test Section• Recuperator and Pump Bypass

Lines• Oxygen Control System• Initial Tests - Late 2001• 48-h Test - August 2002

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Delta Loop TRACE ModelDelta Loop TRACE Model

Delta Loop TRAC Model

960962964230

210

220

250240

PbBi intermediate layer

Water Coolant200

FILL

BREAKBREAKFILL

240 250

220

210

Sump Tank

Pump (insidesump tank)

Bypass Line

10

20

30

50

60

70

80

100

160

110120

140

150

40

Recuperator

Shell Side

Heater

Test SectionPressure Boundary

950

970

10

20 30

40

50 60

70 80

120

130

140

150

170

160

170

Tube Side

Pump Bypass Line

Recuperator Bypass Line

145

145

155

150

180 185

180

190

190195

Valve positions: (1) open for normal operation, closed for natural convection operation(2) closed for normal operation, open for natural convection operation(3) normally closed for both normal and natural convection operation but can be opent to bypass recuperator for natural convection operation

5° 90

90

9595

Expansion TankPressure Boundary

(2)

100110

(1)

(2)

(3)

(1)

130

•TC901

•TC902 •TC903

•TC904•TC905

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48-h Test Data Comparison48-h Test Data Comparison

Comparison of test data to calculated results

325

350

375

400

425

20000 40000 60000 80000 100000 120000 140000 160000

Time (s)

Tem

per

atu

re (

°C)

TC901 HX outlet

TC902 Recup. outlet

TC903 Recup. inlet

TC904 Heater outlet

TC905 Heater inlet

Calculated

Calculated

Calculated

Calculated

Calculated

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TRACE Applications for the LANSCE-1L Test Facility Safety Study

TRACE Applications for the LANSCE-1L Test Facility Safety Study

• LANSCE-1L test facility primary cooling system design study.

– The main objective is to study the effect of the piping connections among the window, upper target, and lower target on the beam shutdown resulting from melting of the window.

– Three piping layouts were studied.• Parallel connection outside the crypt (current layout).• Series connection outside the crypt.• Series connection inside the crypt.

• Loss-of-pump with beam on accident Analysis.

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Risk-Consequence Policy for LANLRisk-Consequence Policy for LANL

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Target Cooling System SketchTarget Cooling System Sketch

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LANSCE-1L Test Facility LayoutLANSCE-1L Test Facility Layout

• LANSCE 1L-area target crypt consists of an upper target, a lower target, two windows, a lower reflector, an upper reflector, outer reflectors, beam stop, and hydrogen moderator.

• The lower and upper targets and the window are cooled by a closed loop cooling system.

• The lower and upper reflectors and the beam stop are cooled by a separate closed loop cooling system.

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TRACE Model for the Target Cooling System

TRACE Model for the Target Cooling System

Surge TankHeat Exchanger

Pump 1

pump 2

Window

Top target

Lower target

1

5

10

15

20

3032343638

4042444648

5055

65

707577

8081

96

100105110

115

120125 130 135 140 145 150

155

160

5252 50

5560

39

38

49

48

36 34 32

46 44 42

30

40

20

15

160

155

5

1

150145140135130125120

115

70

80

100

7576

81

105

95

110

77

96

111

118116118116

8283

8485

8687

8889

9091

92

9495

93

82

83 84

8586

87 88

8990

91 92

9394

97

60

62

64

64

62

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Three Piping Layouts in the CryptThree Piping Layouts in the Crypt

Inletoutlet

Window

Top Target

Lower Target

Inletoutlet

Window

Top Target

Lower Target

Crypt Vessel

Crypt Vessel

Series Connection outside the crypt vessel

Series connection inside the crypt vessel

Inlet plenumoutlet plenum

Window

Top Target

Lower Target

Crypt VesselCrypt Vessel

Parallel Connection outside the crypt vessel

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TRACE ResultsTRACE Results

• For a loss-of-pump accident, the TRACE results show that the window will remain cool even with the beam on throughout the transient.

• Window performance is independent of the piping layouts in the crypt. The idea of passively shutting down the beam based on melting the window will not work.

• The flow channel of the window never dries out and the gas volume fraction oscillates about 0.2.

• The window is heated to about 490 K but the upper target is heated to 3200 K at 100 s.

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TRACE ResultsTRACE Results

Gas Volume Fraction (alpn-075004: window, alpn-081001 and alpn-083001: top-two-flow channels of the upper target)

UNCLASSIFIED

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TRACE ResultsTRACE Results

Maximum average rod temperature (tramax-911: window, tramax-901, tramax-902 and tramax-903: target-top-three plates)

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UNCLASSIFIED

Loss-of-Pump Accident with Beam On Analysis

Loss-of-Pump Accident with Beam On Analysis

640

635

615

610

680

670 630

625

80

605

603

601

602

81

600

655

660

660

655

603604

605600

625

630

670

680

635

640

610

615

teetee

tee

tee

tee

tee

valve

valve

valve

valvevalve

breakbreak

fill heat structure

*The overall TRACE model consists of the system model shown previously, and the crypt model shown here.

TRACE Crypt Model:

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TRACE ResultsTRACE Results

• The upper target canister reaches the melting temperature (1500 K) at about 41s.

• The cooling system is completely drained at about 140 s• After the cooling system is completely drained, the target

would be cooled by radiation to the cool outside reflectors.• A TRACE radiation model was developed and the

preliminary results show that the upper target reaches about 3200 K at about 300 s and keeps at that temperature throughout the transient.

UNCLASSIFIED

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TRACE ResultsTRACE Results

Gas Volume Fractions in the Crypt

0.8600

0.8800

0.9000

0.9200

0.9400

0.9600

0.9800

1.0000

0.0 20.0 40.0 60.0 80.0 100.0 120.0 140.0 160.0

Time (s)

alp6001alp6003alp6551alp6554

Gas volume fractions in the crypt (alp6551: bottom, alp6554: middle, alp6001 and alp6003: top-two levels)

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TRACE ResultsTRACE Results

Surface Temperatures for the Lumped Steel Plates, Upper and Lower Targe

0.00

500.00

1000.00

1500.00

2000.00

2500.00

3000.00

3500.00

4000.00

0.0 20.0 40.0 60.0 80.0 100.0 120.0 140.0 160.0

Time (s)

rft812rft901rft910

Surface temperatures (rft812: lumped upper steel plate, rft901: upper target, rft910: lower target)