benchmark tutorial -- ii - availability

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Benchmarking Experiments for Criticality Safety and Reactor

Physics Applications – II –Tutorial

John D. Bess and J. Blair Briggs – INL

Ian Hill (IDAT) – OECD/NEA

This paper was prepared at Idaho National Laboratory for the U.S. Department of

Energy under Contract Number (DE-AC07-05ID14517)

2012 ANS Annual Meeting

Chicago, Illinois

June 24-28, 2012

Outline

I. Introduction to Benchmarkinga. Overviewb. ICSBEP/IRPhEP

II. Benchmark Experiment Availabilitya. DICE Demonstrationb. IDAT Demonstration

III. Dissection of a Benchmark Reporta. Experimental Datab. Experiment Evaluationc. Benchmark Modeld. Sample Calculationse. Benchmark Measurements

IV. Benchmark Participation

2

BENCHMARK EXPERIMENT AVAILABILITY

3

4

Contribution by Country – ICSBEP Evaluations

Distribution of the 532 Evaluations in the 2011 Publication of theInternational Handbook of Evaluated Criticality Safety Benchmark Experiments

5

Contribution by Country – ICSBEP Configurations

Distribution of the Estimated 4550 Configurations in the 2011 Publication of the International Handbook of Evaluated Criticality Safety Benchmark Experiments

6

• Experiment title

• Identification number(Fissile Material) - (Physical Form) - (Spectrum) - (Three-Digit Numerical Identifier)

Subcritical measurements are denoted by including the letters “SUB” at the beginning of the identifier.

• Key words

A list of words that describe key features of the experiment is provided.

ICSBEP Evaluation Identification

Fissile Material Physical Form Spectrum

Plutonium PU Metal MET Fast FAST

Highly Enriched Uranium HEU Compound COMP Intermediate-Energy INTER

Intermediate Enriched Uranium IEU Solution SOL Thermal THERM

Low Enriched Uranium LEU Miscellaneous MISC Mixed MIXED

Uranium-233 U233

Mixed Plutonium – Uranium MIX

Special Isotope SPEC

7

Distribution of Benchmark Configurations

0

200

400

600

800

1000

1200

1400

1600

Pu HEU IEU LEU U233 MIX SPEC

717

1384

184

1520

244

482

20

118

576

4179

1153

20

563

517

64117

227

7235

284

79

1264

6

277

760 77

Nu

mb

er

of

co

nfi

gu

rati

on

s

Total

Metal

Solution

Compound

Misc.

8

Plutonium Systems – Fuel Type & Form(716 Configurations)

PU - Metal Systems

PU - Solution Systems

563 thermal

PU - Compound Systems

6 fast4 intermediate

17 thermal

8 mixed

111 fast

1 mixed2 thermal

4 intermediate

Highly Enriched Uranium Systems(1384 Configurations)

HEU - Metal Systems

HEU - Solution Systems

514 thermal

HEU - Compound Systems

388 fast

137 thermal36 mixed

14 intermediate

218 thermal

47 mixed

3 intermediate

15 intermediate

2 thermal

HEU - Metal & Solution Systems

5 thermal

HEU – Compound & Solution Systems

5 fast

9

Intermediate and MixedEnrichment Uranium Systems(184 Configurations)

IEU - Metal Systems

41 fast

IEU - Solution Systems

64 thermal

IEU - Compound Systems

46 thermal

17 intermediate2 fast14 mixed

10

Low Enriched Uranium Systems(1520 Configurations)

LEU - Metal Systems

LEU - Solution Systems

117 thermal

LEU - Compound Systems

79 thermal

1258 thermal

LEU – Mixed Compound & Solution Systems

60 thermal

1 fast5 mixed

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Uranium-233 Systems(244 Configurations)

U233 - Metal Systems

10 fast

U233 - Solution Systems

190 thermal

29 intermediate8 mixed

U233 - Compound Systems

6 thermal

1 thermal

12

Mixed Plutonium-Uranium Systems (482 Configurations)

MIX - Metal Systems

MIX - Solution Systems

72 thermal

MIX - Compound Systems

255 thermal

48 fast

4 intermediate 1 mixed

MIX - Compound & Solution Systems

56 thermal

5 fast

MIX – Metal & Compound

13 fast

3 intermediate17 mixed

8 mixed

13

Special Isotope Systems(20 Configurations)

SPEC - Metal Systems

20 fast

14

Neptunium-237

Plutonium-238

Plutonium 242

Curium-244

ICSBEP Benchmark Generation Over the Years

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High Quality Benchmark Experiments

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Even Higher Quality Benchmark Experiments

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IRPhEP Evaluation Identification

• Experiment title

• Identification number(Reactor Name) - (Reactor Type) - (Facility Type) - (Three-Digit Numerical Identifier)

(Measurement Type(s))

Reactor Type Facility Type Measurement Type

Pressurized Water Reactor PWR Experimental Facility EXP Critical Configuration CRIT

VVER Reactors VVER Power Reactor POWER Subcritical Configuration SUB

Boiling Water Reactor BWR Research Reactor RESR Buckling & Extrapolation Length BUCK

Liquid Metal Fast Reactor LMFR Spectral Characteristics SPEC

Gas Cooled (Thermal) Reactor GCR Reactivity Effects REAC

Gas Cooled (Fast) Reactor GCFR Reactivity Coefficients COEF

Light Water Moderated Reactor LWR Kinetics Measurements KIN

Heavy Water Moderated Reactor HWR Reaction-Rate Distributions RRATE

Molten Salt Reactor MSR Power Distributions POWDIS

RBMK Reactor RBMK Nuclide Composition ISO

Fundamental FUND Other Miscellaneous Types of Measurements

MISC

IRPhEP 2012 Available Benchmarks (52 + 4 Drafts)

• PWR – 3– CREOLE, VENUS, SSCR– +2 VENUS Drafts

• VVER – 2– Pfacility, ZR6– +1 LR0 Draft

• BWR – 0

• LMFR – 20– BFS1, BFS2, FFTF, JOYO,

SNEAK, ZEBRA, ZPR, ZPPR

• GCR – 6– ASTRA, HTR10, HTTR,

HTR-PROTEUS– +1 VHTRC Draft

• GCFR – 0

• LWR – 8– CROCUS, DIMPLE,

IPEN/MB01, KRITZ, TCA

• HWR – 2– DCA, ZED2

• MSR – 0

• RBMK – 1– RBMKCF

• FUND – 10– ATR, BFS1, BFS2, NRAD,

PBF, RHF, SCCA, ZEBRA

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IRPhEP 2012 Available Benchmark Data

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Demonstration of ICSBEP Handbook

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Demonstration of IRPhEP Handbook

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Requesting the Handbooks

• For OECD/NEA Member Countries and Participants in the Handbooks

• ICSBEP Handbook

• IRPhEP Handbook

• DVD and Online Access

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http://icsbep.inl.gov/

http://www.oecd-nea.org/science/wpncs/icsbep/

http://irphep.inl.gov

http://www.oecd-nea.org/science/wprs/irphe/

Current OECD/NEA Member Countries (2012)

Australia France Luxembourg Slovak Republic

Austria Germany Mexico Slovenia

Belgium Greece Netherlands Spain

Canada Hungary New Zealand Sweden

Chile Iceland Norway Switzerland

Czech Republic Ireland Poland Turkey

Denmark Israel Portugal United Kingdom

Estonia Italy Republic of Korea United States

Finland Japan Russian Federation (2013)

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DICE DEMONSTRATIONDatabase for the International CriticalitySafety Benchmark Evaluation Project

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Critical/Subcritical Data

26

Alarm/Shielding Data

27

Fundamental Physics Data

28

Correlation Matrix

29

Search by Evaluator

30

Search by Varying Parameter

31

Search by Laboratory

32

Search by Dates

33

Search by Fuel Form/Fissile Material

34

Search by Material(s) in Fuel Region

35

Search by Fuel Isotopic Content

36

Search by Pu/(U+Pu) Ratio

37

Search by Moderator/Coolant Material

38

Search by Neutron Absorbing Material

39

Search by Geometry

40

Search by EALF

41

Search by Fission Energy Distribution

42

Calculation Codes and Cross Section Data

43

Search by Neutron Balance Data

44

Search on Neutron Balance for Cr (Natural)

45

Neutron Balance Data Summary

46

Detailed Balance Data

47

Search HEU-SOL-THERM Benchmarks

48

HEU-SOL-THERM Search Results

49

Spectra Plots

50

Search U233-SOL

51

U233-SOL Search Results

52

Sensitivity Plots

53

Comparison of ABBN and TSUNAMI Data

54

HTML Summary Information

55

Recent Examples of DICE Implementation – I

• Slovenia– Identify experiments with significant captures in boron

to re-examine the treatment of boron uncertainty for natural isotopic abundance of 10B

• Example– Search Neutron Absorbing Material = Boron

– Apply Energy and Spectra = Fission options

– View Sensitivity Plots: HMF010, LCT050, & HST013

56

Search Neutron Absorbing Material = Boron

57

Apply Energy and Spectra = Fission options

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View Sensitivity Plots: HMF010, LCT050, & HST013

59

Look at Plot of Boron Concentration (g/L)

60

Recent Examples of DICE Implementation – II

• U.S.– Identify plutonium experiments with low EALF to

evaluate sensitivity to low energy eta (# fission neutrons produced per absorption in the fuel).

• Example– Search Identification = PU and EALF < 0.06 eV

– Apply Energy and Spectra = EALF (eV) option

– View Spectra Plots: PST003-008 & PST009-002 (n,f)

– Now Search PU without EALF limit

– Add Spectra Plot: PMF004-009 (n,f)

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Search Identification = PU and EALF < 0.06 eV

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Apply Energy and Spectra = EALF (eV) option

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Look at Plot of EALF (eV)

64

View Spectra Plots: PST003-008 & PST009-002 (n,f)

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Add Spectra Plot: PMF004-009 (n,f)

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Recent Examples of DICE Implementation – III

• U.S.– Identify U-Zr-H experiments and see how well they can

be calculated

• Example– Search Fuel Form/Fissile Material = Uranium Hydride

– Search Fuel Region = Zr (Natural)

– Apply Benchmark and Calculated keff options

– Plot C/E Results• X-axis = Case Identification

• Y-axis = C/E

• Series = Library or Code Name

67

Search Fuel Form/Fissile Material = Uranium Hydride

68

Apply Benchmark and Calculated keff options

69

Plots C/E Results – I

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Plots C/E Results – II

71

Validation, Interpretation and Bias Estimation (VIBE)

• Plug-in for DICE developed by SCALE team at ORNL

• GUI to identify and display available TSUNAMI sensitivity data

• Exported for criticality code validation studies

• ORNL is increasing the availability of TSUNAMI files for ICSBEP benchmark data

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Questions on DICE?

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IDAT DEMONSTRATIONInternational Reactor Physics ExperimentEvaluation Database and Analysis Tool

74

IDAT

DEMO

Questions on IDAT?

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UNAVAILABLE BENCHMARK DATA…NOW WHAT?

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Are We There Yet?

• Initially thought all benchmarks would be completed in less than a decade

• Constant need for updated/refined cross section data

• Demand for materials, conditions, methods, safety, etc., evolve with time

• Numerous nuclear experiments performed world-wide

– In danger of losing even more of our nuclear heritage

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What Benchmark Data Are We Missing?(Some Examples)

ICSBEP

• Intermediate Spectra

• Intermediate Enriched Uranium

• Uranium Hexafluoride

• Uranium-10Mo

• Nitride Fuels

• Minor Actinides

• Subcritical Methods

IRPhEP

• BWR

• GCFR

• MSR

• Power Distributions

• Isotopic Measurements– Burnup

• Plutonium Dioxide Fuel

• Similar needs as ICSBEP

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WHAT BENCHMARK DATA ARE YOU MISSING?

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Finding or Designing Benchmark Data

1. Literature Search– OSTI

– NASA Technical Reports

– Laboratory Reports• Digitization and Data

Recovery Projects

– Journals and Conference Proceedings

2. Benchmark Analysis

1. New Experiments– CeDT/NCSP

• NCERC @ NNSS

– Other Critical Facilities

– Operational Reactor Facilities

• RERTR – LEU Conversions

2. Experiment Design Process

3. Benchmark Analysis

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Questions?

81

Mihalczo

HEU

Sphere