Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1765 IRPHE2015-HANDBOOK.
last modified: 29-MAY-2015 | catalog | new | search |

NEA-1765 IRPHE2015-HANDBOOK.

IRPHE2015-HANDBOOK, International Handbook of Evaluated Reactor Physics Benchmark Experiments

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1. NAME OR DESIGNATION

IRPHE2015-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
IRPHE2015-HANDBOOK NEA-1765/11 Arrived 29-MAY-2015

Machines used:

Package ID Orig. computer Test computer
NEA-1765/11 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:

http://www.oecd-nea.org/tools/ierequest/start/package/NEA-1765%2511

 

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 2015 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments contains data from 143 experimental series that were performed at 50 reactor facilities. To be published as approved benchmarks the experiments must be evaluated against agreed technical criteria and reviewed by the IRPhE Technical Review Group. A total of 139 of the 143 evaluations are published as approved benchmarks. The remaining four evaluations are published as draft documents only.

 

New to the handbook are benchmark specifications for selected measurements from the Babcock and Wilcox (B&W) Spectral Shift Reactor Lattice Experiment that was performed to study the nuclear properties of rod lattices moderated by D2O-H2O mixtures.

 

More information about this edition is available at: https://www.oecd-nea.org/science/wprs/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-1765/11 29-MAY-2015 Arrived restricted
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10. REFERENCES
NEA-1765/11, included references:
- International Handbook of Evaluated Reactor Physics Benchmark Experiments
NEA/NSC/DOC(2006)1, NEA No. 7258, March 2015 Edition (OECD/NEA)
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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:
Nuclear Science Division
OECD/NEA Data Bank
12 boulevard des Iles
92130 Issy les Moulineaux (France)

 

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.

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16. MATERIAL AVAILABLE
NEA-1765/11
DVD with reactor physics evaluations
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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.