Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1765 IRPHE2021-HANDBOOK
last modified: 09-NOV-2022 | catalog | new | search |

NEA-1765 IRPHE2021-HANDBOOK

IRPHE2021-HANDBOOK, International Handbook of Evaluated Reactor Physics Benchmark Experiments

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1. NAME OR DESIGNATION

IRPHE2021-HANDBOOK.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

Program name Package id Status Status date
IRPHE2021-HANDBOOK NEA-1765/16 Arrived 09-NOV-2022

Machines used:

Package ID Orig. computer Test computer
NEA-1765/16 Many Computers
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3. DESCRIPTION

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/tools/ierequest/start/package/NEA-1765%2516

 

The evaluation process entails the following steps:

  1. Identify a comprehensive set of reactor physics experimental measurements data,

  2. 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,

  3. Compile the data into a standardized format,

  4. Perform calculations of each experiment with standard reactor physics codes where it would add information,

  5. 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 2021 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments contains data from 169 experimental series that were performed at 57 nuclear facilities. A total of 165 of the 169 evaluations are published as approved benchmarks. The remaining four evaluations are published as draft documents only.

 

The cover of the handbook shows the ZPR-9 machine at Argonne National Laboratory-East in Illinois to support development of a gas cooled fast reactor (GCFR) in the United States. Newly evaluated criticality, control worth, and spectral characteristics measurements from the ZPR-9 have been added to this edition of the handbook.

 

More information about this edition is available at: https://www.oecd-nea.org/jcms/pl_20279/international-handbook-of-evaluated-reactor-physics-benchmark-experiments-irphe  

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8. RELATED INFORMATION

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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9. STATUS
Package ID Status date Status
NEA-1765/16 09-NOV-2022 Arrived restricted
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10. REFERENCES
NEA-1765/16, included references:
- NEA Nuclear Science Committee:
International Handbook of Evaluated Criticality Safety Benchmark Experiments
(Edition 2021)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

This project is being carried out under the auspices of the OECD Nuclear Energy Agency

 

Contact at NEA:

Tatiana Ivanova

Division of Nuclear Science and Education

46 quai Alphonse Le Gallo

92100 Boulogne-Billancourt

France

cps-irphe (at) oecd-nea.org

 

Contact at INL (USA):

Mark D. DeHart

Idaho National Laboratory

2525 North Fremont

Idaho Falls, ID 83415-3855

USA

mark.dehart (at) inl.gov

 

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.

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16. MATERIAL AVAILABLE
NEA-1765/16
International Handbook of Evaluated Criticality Safety Benchmark Experiments
(Edition 2021)
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: evaluated data, experiment, fast reactors, high-temp reactor, pressurized water reactor, reactor physics.