The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at various nuclear facilities around the world. The benchmark specifications are intended for use by reactor designers, safety analysts and nuclear data evaluators to validate calculational techniques and data. The Handbook is a product of the International Reactor Physics Evaluation (IRPhE) Project, conducted by the OECD Nuclear Energy Agency (NEA). While co-ordination and administration of the IRPhE Project is undertaken by the NEA, each participating country is responsible for the administration, technical direction, and priorities of the project within their respective countries. Access to some of the information and data included in this handbook may be restricted; full conditions for access are available below.
The 2020 edition contains data from 167 different experimental series that were performed at 56 different nuclear facilities. Some 163 of the 167 evaluations are published as approved benchmarks. The remaining four evaluations are published as draft documents only. All draft documents were reviewed by the International Reactor Physics Evaluation (IRPhE) Technical Review Group (TRG). Example calculations are presented; however, these calculations do not constitute validation or endorsement of the codes or cross section data. The IRPhE project is patterned after the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and is closely co-ordinated with the ICSBEP. Some benchmark data are applicable to both nuclear criticality safety and reactor physics technology. Some have already been evaluated and published by the ICSBEP, but have been extended to include other types of measurements besides the critical configuration.
Comments (recommendations, additions, deletions and corrections), which may be of use in improving this handbook, should be addressed to:
John D. Bess
Idaho National Laboratory
2525 North Fremont
Idaho Falls, ID 83415-3855
United States of America
The Handbook is published in electronic format (pdf files), where the experiments are grouped into evaluations, categorised by: 1) reactor name; 2) reactor type; 3) facility type; and 4) measurement type.
The IRPhE Handbook, featuring the IRPhE Database and Analysis Tool (IDAT), is distributed on DVD and online. It can be requested by completing the form below.
The Handbook is available to authorised requesters from the OECD member countries and to contributing establishments from non-OECD countries. Other requests are handled on a case by case basis. Read the restrictions and disclaimer, and about providing feedback.
Even if you have had access to the online version of the Handbook in previous years, the request must be renewed for each new edition.
If you have already been authorised access to the 2020 edition, you can access it below:
If you have already been authorised access to the 2019 edition, you can access it below:
If you have already been authorised access to the 2018 edition, you can access it below:
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various critical facilities around the world.
The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook information. Selected information from each configuration was entered into IDAT, such as the measurements performed, benchmark values, calculated values and materials specifications of the benchmark. In many cases this is supplemented with calculated data such as neutron balance data, spectra data, k-eff nuclear data sensitivities, and spatial reaction rate plots.
The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nuclear power systems.