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Title: Intrinsic value of the international benchmark projects, ICSBEP and IRPhEP, for advanced reactor development

Journal Article · · Frontiers in Energy Research
ORCiD logo [1];  [2]; ORCiD logo [2];  [2];  [3];  [3]; ORCiD logo [3];  [4]; ORCiD logo [5]; ORCiD logo [6]
  1. JFoster & Associates, LLC, Idaho Falls, ID (United States)
  2. Organisation for Economic Co-operation and Development (OECD), Paris (France). Nuclear Energy Agency (NEA)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  4. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  5. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  6. Commissariat à L’énergie Atomique et aux Energies Alternatives, Paris (France)

The International Criticality Safety Benchmark Evaluation Project, a sanctioned program under the auspices of the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development, has been a highly successful and productive collaboration, now encompassing over 5,000 evaluated experimental benchmarks trusted and relied upon throughout the international nuclear communities. The success of this project led to the development of the International Reactor Physics Experiment Evaluation Project, which is dedicated to the evaluation of benchmark experiment data to sustain current and future reactor physics validation needs. These exemplary programs, and their widely utilized handbooks, serve as gold standards to which other databases strive to emulate. The purpose of the two projects is to preserve modern and legacy experimental data and evaluate it in a standardized handbook format to provide quality benchmarks to support modern and future criticality safety and reactor physics validation. These two projects have often served as the mechanism through which historic and modern neutronics experiments are evaluated and shared across international borders, to best provide unique, high-quality peer-reviewed, and often otherwise unavailable, benchmark data. The contents of these handbooks are utilized not only in validating criticality safety, reactor physics, and advanced reactor calculations, but are used to validate neutronics calculations and nuclear data for most other nuclear applications. This paper discusses both international programs and available content to enable advanced reactor design validation.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1969136
Report Number(s):
INL/JOU-22-70024-Rev000; TRN: US2313382
Journal Information:
Frontiers in Energy Research, Vol. 11, Issue 2023; ISSN 2296-598X
Publisher:
Frontiers Research FoundationCopyright Statement
Country of Publication:
United States
Language:
English

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Figures / Tables (15)