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The purpose of the International Reactor Physics Experiment Evaluation (IRPhE) Project is to provide an extensively peer-reviewed set of reactor physics-related integral data that can be used by reactor designers and safety analysts to validate the analytical tools used to design next-generation reactors and establish the safety basis for operation of these reactors. This work of the IRPhE Project is formally documented in the 'International Handbook of Evaluated Reactor Physics Benchmark Experiments', a single source of verified and extensively peer-reviewed reactor physics benchmark measurements data.
The IRPhE Handbook is available on DVD or by online access. Either may be requested by completing the package request form: https://www.oecd-nea.org/science/wprs/irphe/handbook.html
The evaluation process entails the following steps:
Identify a comprehensive set of reactor physics experimental measurements data,
Evaluate the data and quantify overall uncertainties through various types of sensitivity analysis to the extent possible, verify the data by reviewing original and subsequently revised documentation, and by talking with the experimenters or individuals who are familiar with the experimental facility,
Compile the data into a standardized format,
Perform calculations of each experiment with standard reactor physics codes where it would add information,
Formally document the work into a single source of verified and peer reviewed reactor physics benchmark measurements data.
The International Handbook of Evaluated Reactor Physics Benchmark Experiments contains reactor physics benchmark specifications that have been derived from experiments that were performed at nuclear facilities around the world. The benchmark specifications are intended for use by reactor designers, safety analysts and nuclear data evaluators to validate calculation techniques and data. Example calculations are presented; these do not constitute a validation or endorsement of the codes or cross-section data.
The 2018 edition of the International Handbook of Evaluated Reactor Physics Experiments contains data from 159 experimental series that were performed at 54 nuclear facilities. A total of 156 of the 159 evaluations are published as approved benchmarks. The remaining five evaluations are published as draft documents only.
The cover of the handbook shows the Japan Atomic Energy Agency’s Fast Critical Assembly (FCA) reactor – a horizontal split-table design, loaded with plate fuel arranged within drawers. Newly evaluated measurements from FCA have been added to this edition of the handbook.
More information about this edition is available at: https://www.oecd-nea.org/science/wprs/irphe/
International Criticality Safety Benchmark Evaluation Project (ICSBEP).
IRPHE/B&W-SS-LATTICE, Spectral Shift Reactor Lattice Experiments
IRPHE-JAPAN, Reactor Physics Experiments carried out in Japan
IRPHE/JOYO MK-II, JOYO MK-II core management and characteristics database
IRPhE/RRR-SEG, Reactor Physics Experiments from Fast-Thermal Coupled Facility
IRPHE-SNEAK, KFK SNEAK Fast Reactor Experiments, Primary Documentation
IRPhE/STEK, Reactor Physics Experiments from Fast-Thermal Coupled Facility
IRPHE-ZEBRA, AEEW Fast Reactor Experiments, Primary Documentation
IRPHE-DRAGON-DPR, OECD High Temperature Reactor Dragon Project, Primary Documents
IRPHE-ARCH-01, Archive of HTR Primary Documents
IRPHE/AVR, AVR High Temperature Reactor Experience, Archival Documentation
IRPHE-KNK-II-ARCHIVE, KNK-II fast reactor documents, power history and measured parameters
IRPhE/BERENICE, effective delayed neutron fraction measurements
IRPhE-TAPIRO-ARCHIVE, fast neutron source reactor primary documents, reactor physics experiments
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This project is being carried out under the auspices of the OECD Nuclear Energy Agency
Contact at NEA:
Nuclear Science Division
46 quai Alphonse Le Gallo
Contact at INL (USA):
John D Bess
Idaho National Laboratory
2525 North Fremont
Idaho Falls, ID 83415-3855 (United States)
The International Handbook of Evaluated Reactor Physics Benchmark Experiments was prepared by a working party comprised of experienced reactor physics personnel from Argentina, Belgium, Brazil, Canada, P.R. of China, Czech Republic, France, Germany, Hungary, Italy, Japan, Republic of Korea, Russian Federation, Serbia, Slovenia, South Africa, Sweden, Switzerland, United Kingdom, and the United States of America.
The IRPhE handbook is available to authorised requesters from the NEA member countries and to contributing establishments from non-member countries. Other requests are handled on a case by case basis.
Keywords: evaluated data, experiment, fast reactors, high-temp reactor, pressurized water reactor, reactor physics.