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International Reactor Physics Benchmark Experiments (IRPhE) ProjectThe International Reactor Physics Benchmark Experiments (IRPhE) Project aims to provide the nuclear community with qualified benchmark data sets by collecting reactor physics experimental data from nuclear facilities, worldwide. More specifically the objectives of the expert group are as follows:
IRPHE meeting for the March 2010 Handbook edition Paris, France the 20-23 Ocotober 2009Registration (only for expert group members)Current activitiesThe group is currently:
Fourth edition and availabilityThe fourth edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments was published in March 2009 (ISBN 978-92-64-99055-5) and contains reactor physics benchmark specifications that have been derived from experiments that were performed at various nuclear experimental facilities around the world. The benchmark specifications are intended for use by reactor physics personnel to validate calculational techniques. This Edition contains data from 36 different experimental series that were performed at 21 different reactor facilities. A few of these evaluations are published as DRAFT documents only. Draft documents have been reviewed by the IRPhEP Technical Review Group (TRG); however, all action items could not be completed or reviewed in time for the final publication or, in most cases, the TRG felt it necessary to review the revised evaluations before giving final approval. The Handbook is organized in a manner that allows easy inclusion of additional evaluations, as they become available. Additional evaluations are in progress and will be added to the handbook periodically. The Handbook is published in electronic format (pdf files) on DVD, where the experiments are grouped into evaluations, categorised by (1) Reactor Name, (2) Reactor Type, (3) Facility Type, and (4) Measurement Type. The Handbook was prepared by a working party comprised
of
experienced
reactor physics personnel from Belgium, Brazil, Canada, P.R. of China,
France,
Germany, Hungary, Japan, Republic of Korea, Russian Federation,
Slovenia,
Switzerland, United
Kingdom, and the United States. Handbook contents March 2009 Edition
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Evaluations |
TITLE |
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FUND |
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ATR-FUND-RESR-001 CRIT |
Advanced Test
Reactor: Serpentine Arrangement of Highly Enriched
Water-Moderated Uranium-Aluminide Fuel Plates Reflected by Beryllium |
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BFS1-FUND-EXP-001 CRIT-SPEC-COEF-RRATE |
Experimental Program Performed at the BFS-97, -99, -101 Assemblies - Critical Experiments with Heterogeneous Compositions of Plutonium, Depleted Uranium Dioxide and Polyethylene |
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BFS1-FUND-EXP-002 CRIT-SPEC-REAC-RRATE |
Experimental Program Performed at the BFS-42 Assembly - k-infinity Experiments for 238U in Fast Neutron Spectra: Measurements with Plutonium Mixed with Depleted Uranium Dioxide and Polyethylene |
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BFS1-FUND-EXP-003 CRIT-SPEC-COEF-RRATE |
Experimental Program Performed at the BFS-57and -59 Assemblies - Critical Experiments with Heterogeneous Compositions of Enriched Uranium or Plutonium, Depleted Uranium Dioxide and Polyethylene |
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BFS2-FUND-EXP-001 CRIT-SPEC-REAC |
Experimental
Program Performed at the BFS-31 Assemblies - k-infinity Experiments for
238U in Fast Neutron Spectra: Measurements
with Plutonium Mixed with Depleted Uranium Dioxide
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GCR |
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ASTRA-GCR-EXP-001 CRIT |
Graphite Annular Core Assemblies with Fuel Elements Containing UO2 Coated Fuel Particles |
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HTR10-GCR-RESR-001 CRIT |
Evaluation of the Initial Critical Configuration of the HTR-10 Pebble-Bed Reactor |
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HTTR-GCR-RESR-001 CRIT-SUB-REAC-COEF-KIN-RRATE |
Evaluation of
the Start-Up
Core Physics Tests at Japan’s High Temperature Engineering Test Reactor
(Fully-Loaded Core) |
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HWR |
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DCA-HWR-RESR-001 CRIT-SPEC-RRATE |
Deuterium Critical Assembly with 1.2% Enriched Uranium Varying Coolant Void Fraction and Lattice Pitch |
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HFR-HWR-RESR-001 CRIT |
Evaluation of
Measurements
Performed on the French High Flux Reactor (HFR) |
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LMFR |
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BFS1-LMFR-EXP-001 CRIT-SPEC-COEF-KIN-RRATE |
BFS-73-1 Assembly: Experimental Model of Sodium-Cooled Fast Reactor with Core of Metal Uranium Fuel of 18.5% Enrichment and Depleted Uranium Dioxide Blanket |
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BFS2-LMFR-EXP-002 CRIT-SPEC-RRATE |
BFS-62-3A Experiment: Fast Reactor Core with U and U-Pu fuel of 17% Enrichment and Partial Stainless Steel Reflector |
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JOYO-LMFR-RESR-001 CRIT-REAC-COEF |
Japan's Experimental Fast Reactor JOYO MK-Icore: Sodium-Cooled Uranium=Plutonium Mixed Oxide Fueled Fast Core Surrounded by UO2 Blanket |
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ZEBRA-LMFR-EXP-001 CRIT-SPEC-REAC-RRATE |
Fast Critical Experiments in Plate and Pin Geometry Form. The ZEBRA CADENZA Cores, Assemblies 22, 23, 24 and 25 |
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ZEBRA-LMFR-EXP-002 CRIT-SPEC-REAC-RRATE |
The ZEBRA MOZART Programme Part 1. MZA and MZB, ZEBRA Assemblies 11 and 12 |
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ZEBRA-LMFR-EXP-003 CRIT-REAC-RRATE |
The ZEBRA MOZART Programme Part 2. MZC and the Control Rod Studies ZEBRA Assembly 12 |
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ZPR-LMFR-EXP-001 CRIT-SPEC-REAC-RRATE |
ZPR-6 Assembly 7: A Cylindrical Assembly with Mixed (Pu,U)-Oxide Fuel and Sodium with a Thick Depleted-Uranium Reflector |
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ZPR-LMFR-EXP-002 CRIT-REAC-RRATE |
ZPR-6
Assembly 7 with High
Pu-240: A Fast Reactor Core With
Mixed (Pu,U)-Oxide Fuel and Sodium and High Pu-240 Zone |
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SNEAK-LMFR-EXP-001 CRIT-SPEC-REAC-RRATE |
SNEAK 7A and
7B:
Pu-Fueled Fast Critical Assemblies in the Karlsruhe Fast Critical
Facility |
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ZPPR-LMFR-RESR-001 CRIT-REAC-RRATE |
ZPPR-10A Experiment: A 650 MWe-Class Sodium-Cooled MOX-Fueled FBR Homogeneous Core Mock-Up Critical Experiment with Two Enrichment Zones and Nineteen Control Rod Positions |
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ZPPR-LMFR-EXP-002 CRIT-SPEC-REAC-RRATE |
ZPPR-9
Experiment: A 650 MWe-Class Sodium-Cooled Mox-Fueled FBR Core
Mock-Up Critical Experiment with Clean Core of Two Homogeneous Zones |
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ZPPR-LMFR-EXP-003 CRIT-SPEC-REAC-RRATE-MISC |
ZPPR-18A
Experiment:
A 1,000 MWe-Class Sodium-Cooled MOX-Fueled FBR Core Mock-Up Critical
Experiment with Two-Homogeneous Zones and Control-Rod Withdrawal, where
Enriched Uranium is used with the Shape of a Sector in the Outer Core |
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ZPPR-LMFR-EXP-004 CRIT-SPEC-REAC-RRATE |
ZPPR-19B
Experiment:
A 1,000 MWe-Class Sodium-Cooled MOX-Fueled FBR Core Mock-Up Critical
Experiment with Two-Homogeneous Zones and Control-Rod Withdrawal, where
Plutonium and Enriched Uranium are used Mixing in the Outer Core |
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LWR |
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CROCUS-LWR-RESR-001 CRIT-REAC-KIN |
Kinetic Parameters and Reactivity Effect Experiments in CROCUS |
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DIMPLE-LWR-RESR-001
CRIT-BUCK-SPEC-REAC-COEF-RRATE |
Light Water Moderated and Reflected Low Enriched Uranium (3 wt.% 235U) Dioxide Rod Lattices DIMPLE S01 |
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DIMPLE-LWR-RESR-002 CRIT-BUCK-SPEC-COEF-RRATE |
Light Water Moderated and Reflected Low Enriched Uranium (3 wt.% 235U) Dioxide Rod Lattices DIMPLE S06 |
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IPEN/MB01-LWR-RESR-001 CRIT-COEF-KIN-RRATE |
Isothermal Experiment of the IPEN/MB-01 Reactor |
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KRITZ-LWR-RESR-001 CRIT-BUCK-RRATE |
KRITZ-2:19
Experiment on
Regular H2O/Fuel Pin Lattices with Mixed Oxide
Fuel at
Temperatures 21.1 and 235.9 °C |
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KRITZ-LWR-RESR-002 CRIT-BUCK-RRATE |
KRITZ-2:1 Experiment on Regular H2O/Fuel Pin Lattices with Low Enriched Uranium Fuel at Temperatures 19.7 °C and 248.5 °C |
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KRITZ-LWR-RESR-003 CRIT-BUCK-RRATE |
KRITZ-2:13
Experiment on
Regular H2O/Fuel Pin Lattices with Low Enriched
Uranium Fuel
at Temperatures 22.1 °C and 243 °C |
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PWR |
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CREOLE-PWR-EXP-001 CRIT-COEF-RRATE-MISC |
CREOLE PWR Reactivity Temperature Coefficient Experiment - UOX and MOX up to 300 °C in EOLE |
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VENUS-PWR-EXP-001 RRATE-POWDIS |
VENUS-1 PWR UO2
Core 2-Dimensional Benchmark Experiment |
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VENUS-PWR-EXP-003 RRATE-POWDIS |
VENUS-3 PWR UO2
Core 3-Dimensional Benchmark Experiment |
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VENUS-PWR-EXP-005 CRIT-SPEC-POWDIS |
Experimental
Study of the
VENUS-PRP Configuration No. 9 |
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VVER |
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PFACILITY-VVER-EXP-001 CRIT-RRATE |
VVER Physics Experiments: Hexagonal (1.27-cm Pitch) Lattices of U(4.4 wt.% 235U)O2 Fuel Rods In Light Water, Perturbed by Boron, Hafnium, or Dysprosium Absorber Rods, or by Water Gap With/Without Aluminium Tubes |
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ZR6-VVER-EXP-001 CRIT-BUCK-SPEC-REAC-COEF-RRATE |
The VVER Experiments: Regular and Perturbed Hexagonal Lattices of Low-Enriched UO2 Fuel Rods in Light Water |
| New or modified in the March 2009 edition |
Much of the work so far realised by the International Reactor Physics Experiments Evaluation Project (IRPhEP), in particular, the evaluation and review of selected benchmark experiments, was possible thanks to substantial funding provided by the Government of Japan. Other countries, currently Belgium, Brazil, Canada, P.R. of China, France, Germany, Hungary, Japan, the Republic of Korea, the Russian Federation, Sweden, Switzerland, the United Kingdom, and the United States of America have contributed evaluations, reviews and data at their own expense. Overall technical coordination of the IRPhEP is directly supported by the United States Department of Energy’s Office of Nuclear Energy with significant in-kind contributions from the parallel OECD NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP), supported in the United States by the Department of Energy’s Office of Facility Management and ES&H Support.
The Fifth IRPhE Technical Review
Meeting was held in Paris on 20-24 October 2008. During this
meeting, experiments evaluations were reviewed that will be added in
the
third edition of the IRPhEP Handbook. The next such meeting will be
held in Paris from 20-23 October 2009.
Password-protected area for IRPhE evaluators and reviewers
Archived NEACRP and NSC documents
Last
updated: 31 March 2009