1. Benchmarking Experiments for
Criticality Safety and Reactor
Physics Applications – II –
Tutorial
John D. Bess and J. Blair Briggs – INL
Ian Hill (IDAT) – OECD/NEA
www.inl.gov
2012 ANS Annual Meeting
Chicago, Illinois
June 24-28, 2012
This paper was prepared at Idaho National Laboratory for the U.S. Department of
Energy under Contract Number (DE-AC07-05ID14517)
2. Outline
I. Introduction to Benchmarking
a. Overview
b. ICSBEP/IRPhEP
II. Benchmark Experiment Availability
a. DICE Demonstration
b. IDAT Demonstration
III. Dissection of a Benchmark Report
a. Experimental Data
b. Experiment Evaluation
c. Benchmark Model
d. Sample Calculations
e. Benchmark Measurements
IV. Benchmark Participation
2
4. Contribution by Country – ICSBEP Evaluations
Distribution of the 532 Evaluations in the 2011 Publication of the
International Handbook of Evaluated Criticality Safety Benchmark Experiments
4
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
5
6. ICSBEP Evaluation Identification
• Experiment title
• Identification number
(Fissile Material) - (Physical Form) - (Spectrum) - (Three-Digit Numerical Identifier)
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
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.
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7. Distribution of Benchmark Configurations
1600
1520
1384 Total
1400
Metal
1264
Solution
1200 Compound
Number of configurations
Misc.
1000
800
717
576
563
600
517
482
400
284 277
244 227
184
200
118 117
79 79 77
35 41 64 60 53 72
7 11 6 20 20
0
Pu HEU IEU LEU U233 MIX SPEC
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8. Plutonium Systems – Fuel Type & Form
(716 Configurations)
PU - Metal Systems
2 thermal 1 mixed
4 intermediate
111 fast
PU - Solution Systems PU - Compound Systems
4 intermediate
8 mixed 6 fast
563 thermal
17 thermal
8
9. Highly Enriched Uranium Systems
(1384 Configurations) HEU - Compound Systems
47 mixed 5 fast 14 intermediate
HEU - Metal Systems
218 thermal
36 mixed
137 thermal
388 fast
HEU - Metal & Solution Systems
15 intermediate
5 thermal
HEU - Solution Systems
3 intermediate
HEU – Compound & Solution Systems
514 thermal
2 thermal
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10. Intermediate and Mixed
Enrichment Uranium Systems
(184 Configurations)
IEU - Metal Systems
41 fast
IEU - Solution Systems IEU - Compound Systems
14 mixed 2 fast 17 intermediate
64 thermal
46 thermal
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11. Low Enriched LEU - Metal Systems
Uranium Systems
(1520 Configurations) 79 thermal
LEU - Compound Systems
LEU - Solution Systems
5 mixed 1 fast
117 thermal
1258 thermal
LEU – Mixed Compound & Solution Systems
60 thermal
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12. Uranium-233 Systems
(244 Configurations) U233 - Metal Systems
1 thermal
10 fast
U233 - Solution Systems U233 - Compound Systems
8 mixed 29 intermediate
190 thermal 6 thermal
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13. Mixed Plutonium- MIX - Compound Systems
5 fast
Uranium Systems 3 intermediate
(482 Configurations) 17 mixed
255 thermal
MIX - Metal Systems
4 intermediate 1 mixed
48 fast MIX - Compound & Solution Systems
56 thermal
MIX - Solution Systems
MIX – Metal & Compound
72 thermal
8 mixed 13 fast
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14. Special Isotope Systems
(20 Configurations)
SPEC - Metal Systems
Neptunium-237
Plutonium-238 20 fast
Plutonium 242
Curium-244
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18. 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 POWDI
S
RBMK Reactor RBMK Nuclide Composition ISO
Fundamental FUND Other Miscellaneous Types of MISC
Measurements
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23. Requesting the Handbooks
• For OECD/NEA Member Countries and
Participants in the Handbooks
• ICSBEP Handbook
http://icsbep.inl.gov/
http://www.oecd-nea.org/science/wpncs/icsbep/
• IRPhEP Handbook
http://irphep.inl.gov
http://www.oecd-nea.org/science/wprs/irphe/
• DVD and Online Access
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24. 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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56. 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
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61. 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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67. 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
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72. Validation, Interpretation and Bias Estimation (VIBE)
• Plug-in for DICE • ORNL is increasing the
developed by SCALE availability of TSUNAMI
team at ORNL files for ICSBEP
• GUI to identify and benchmark data
display available
TSUNAMI sensitivity
data
• Exported for criticality
code validation studies
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77. 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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78. What Benchmark Data Are We Missing?
(Some Examples)
ICSBEP IRPhEP
• Intermediate Spectra • BWR
• Intermediate Enriched • GCFR
Uranium • MSR
• Uranium Hexafluoride • Power Distributions
• Uranium-10Mo • Isotopic Measurements
• Nitride Fuels – Burnup
• Minor Actinides • Plutonium Dioxide Fuel
• Subcritical Methods • Similar needs as
ICSBEP
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