The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...
Published date:
5 March 2021
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) performs specific tasks associa...
Published date:
6 December 2023
Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS), the expert group performed specific tasks associated with radiation transport and shielding aspects of current ...
Published date:
3 March 2020
Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...
Published date:
6 December 2023
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...
Published date:
8 March 2023
The Expert Group on Reactor Systems Multi-Physics (EGMUP) advances the state of the art in establishing processes and procedures for certifying experimental data and benchmarking multi-physics multi-...
Published date:
6 December 2023
The Expert Group on Reactor-based Plutonium Disposition (TFRPD) dealt with the status and trends of reactor physics, fuel performance and fuel cycle issues related to the disposition of weapons-grade...
Published date:
16 December 2020
The Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) dealt with the various aspects of the modelling and design of accelerator shield systems and radiatio...
Published date:
19 November 2021
The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...
Published date:
27 October 2021
First Information Exchange Meeting on the Nuclear Production of Hydrogen, Paris, France, 2-3 October, 2000 - Programme and abstracts
Published date:
24 November 2020
The benchmark will predict the Critical Heat Flux (CHF).
Published date:
22 November 2023
2 -
23 May 2023
Online training & in-person event on 22-23 May 2023 in Bologna, Italy
Published date:
11 December 2023
Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fueled with TRISO-based fuel are a potential molten salt reactor (MSR) design.
Published date:
14 June 2021
Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark
Published date:
2 August 2022
14 -
16 April 2009
Chicago, Illinois, United States
The NEA Nuclear Science Committee (NSC) had previously organised three information exchange meetings to discuss scientific and strategic matters pertaining to the nuclear production of hydrogen. Earl...
Published date:
14 April 2009
Fourth Information Exchange Meeting on thr Nuclear Production of Hydrogen, 13-16 April 2009, Oakbrook, IL, USA - Programme
Published date:
24 November 2020
High-temperature gas-cooled reactors (HTGRs), also known as very-high-temperature reactors (VHTR) are Generation IV reactors that can operate at very high temperatures and use a graphite-moderated ga...
Published date:
22 June 2022
The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
Published date:
24 April 2023
ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings
Published date:
18 November 2019
NEA/NSC/R(2015)4
The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...
Published date:
24 June 2015
NEA/NSC/R(2015)7
The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...
Published date:
2 October 2015
International Fuel Performance Experiments (IFPE) is a data collection of nuclear fuel performance experiments for the purpose of code development and validation.
Published date:
18 January 2024
The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
Published date:
13 December 2022
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 ...
Published date:
9 November 2022
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 inform...
Published date:
17 March 2022
ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings, October 2021.
Published date:
25 October 2021
The International School on Simulation of Nuclear Reactor Systems (SINUS) provides hybrid, hands-on-training encompassing multiphysics modelling and simulation (M&S) and associated validation, verifi...
Published date:
21 December 2023
5 -
6 June 2023
Oregon State University, Corvallis, Oregon, United States
Published date:
20 April 2023
IRPhE Handbook 2019 Edition - Contents
Published date:
30 September 2020
Collected sources of primary documentation for reactor physics benchmarks.
Published date:
14 April 2022
The International Reactor Physics Experiment Evaluation (IRPhE) Technical Review Group provides the nuclear community with qualified benchmark data sets by collecting reactor physics experimental dat...
Published date:
10 November 2022
This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...
Published date:
19 July 2022
Conditions for release, rules and restrictions applying to the Kalinin Unit 3 (Kalinin-3) Transient Benchmark caused by the switching-off of one of the four operating main circulation pumps (MCPs) at...
Published date:
30 September 2020
Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...
Published date:
9 June 2023
The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...
Published date:
19 July 2022
Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on U...
Published date:
19 July 2022
15 -
19 April 2024
Lawrence Livermore National Laboratory (LLNL), California, USA
Published date:
2 February 2024
This publication provides an introduction to minor actinide nuclear properties and discusses some of the arguments in favour of minor actinide recycling, as well as the potential role of thermal reac...
Published date:
18 November 2013
NEA/NSC/R(2016)3
In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...
Published date:
14 June 2016
Multiphysics are simulations using computer applications or software to couple multiple physical events in order to predict or validate the physical real-world outcome.
Published date:
16 October 2020
Published date:
6 December 2017
Neutron noise analysis can be defined as the direct measurement of the kinetics of a nuclear core. This page describes some of the NEA's previous activities on neutron noise analysis in nuclear power...
Published date:
26 July 2021
The meetings took place in April 2024 in the United States.
Published date:
25 April 2024
Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...
Published date:
7 July 2006
This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...
Published date:
1 January 2010
NEA/NSC/R(2020)6
In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...
Published date:
1 June 2021
NEA/NSC/R(2020)7
In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...
Published date:
2 December 2021
NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark
Published date:
2 August 2022
NEA/NSC/DOC(2012)1
Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...
Published date:
4 January 2012
NEA/NSC/DOC(2003)1
21-22 January 2003, Barcelona, Spain
Published date:
1 May 2003