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

• Published in: Frontiers in energy research Vol. 11; no. 2023
• Main Authors: Bess, John D., Ivanova, Tatiana, Hill, Ian, Martin, Julie-Fiona, Briggs, J. Blair, Scott, Lori, DeHart, Mark D., Percher, Catherine, Marshall, B. J., Blaise, Patrick
• Format: Journal Article
• Language: English
• Published: United States Frontiers Research Foundation 28-02-2023; Frontiers Media S.A
• Subjects: advanced reactors; benchmark; criticality safety; experiment; GENERAL STUDIES OF NUCLEAR REACTORS; handbook; ICSBEP; Information Preservation and Dissemination; IRPhEP; NEA; Nuclear Criticality Safety Program (NCSP); nuclear data; OECD
• ISSN: 2296-598X; 2296-598X
• DOI: 10.3389/fenrg.2023.1085788

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 manuscript discusses both international programs and available content to enable advanced reactor design validation.