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/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
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
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
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
The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.
Published date:
6 December 2023
4 -
7 December 2023
NEA, Paris, France
The course is full
Date: 4-7 December 2023
Place: OECD/NEA Headquarters
46, Quai Alphonse Le Gallo
92100 Boulogne-Billancourt (Paris) - FRANCE
Minimum enrollment: 15 participants
Maximum e...
Published date:
17 November 2023
The meetings took place in April 2024 in the United States.
Published date:
25 April 2024
This NEST project aims to integrate SMR research projects from the individual Participating Organisation countries into a broader and more impactful programme. It will include elements of technology ...
Published date:
18 February 2020
Published date:
6 December 2017
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
7 -
10 November 2022
Lord Elgin Hotel - Ottawa, Canada
Published date:
21 November 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
Collected sources of primary documentation for reactor physics benchmarks.
Published date:
14 April 2022
5 -
6 June 2023
Oregon State University, Corvallis, Oregon, United States
Published date:
20 April 2023
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 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
Published date:
13 December 2022
15 -
20 May 2022
Pittsburgh, United States
PHYSOR attracts international experts from all segments of the nuclear industry and scientific community, including vendors, utilities, laboratories, and universities. The theme for this year’s confe...
Published date:
31 January 2022
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
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
The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
Published date:
24 April 2023
21 -
24 May 2024
NEA, Paris, France
Date: 21-24 May 2024
Place: OECD/NEA headquarters
46, Quai Alphonse Le Gallo
92100 Boulogne-Billancourt (Paris) - FRANCE
Minimum enrollment: 8 participants
Maximum enrollment: 22 participant...
Published date:
25 April 2024
The benchmark will predict the Critical Heat Flux (CHF).
Published date:
22 November 2023
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
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 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
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
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 on Physics of Reactor Systems (EGPRS) performs specific tasks associa...
Published date:
6 December 2023
NEA/NSC/R(2019)7
The modelling and simulation of nuclear systems allow scientists and engineers to probe aspects of the operation of these systems beyond what has been precisely measured. This has numerous applicatio...
Published date:
11 October 2022
EGPRS Task Force members met on 3 April 2023.
Published date:
7 April 2023
WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.
Published date:
9 June 2022
The event gathered 129 participants from 75 international institutions.
Published date:
6 October 2022
NEA/NSC/R(2019)6
The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...
Published date:
18 November 2021
Published date:
12 October 2020
NEA/NSC/DOC(1996)5
The OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components was set up in November 1995 in response to a request...
Published date:
1 January 1996
Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.
Published date:
16 June 2023
Published date:
23 February 2016
In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...
Published date:
21 December 2006
In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...
Published date:
7 July 2005
Published date:
16 May 2013
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) workshops, 7-15 December 2020.
Published date:
17 December 2020
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
Published date:
13 June 2023
NEA/NSC/R(2020)5
This benchmark focuses on FHR reactors with plates and triso fuel. Several phases are planned, starting with neutronics on a simple fuel element simulation without burn-up, and gradually extending to...
Published date:
4 June 2021
NEA/NSC/R(2021)5
Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...
Published date:
18 April 2023
The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...
Published date:
25 April 2023
20 -
22 May 2015
Madrid, Spain
Published date:
18 December 2020
14 -
16 May 2014
Garching, Germany
Published date:
21 December 2020
9 -
11 May 2012
Karlsruhe, Germany
Published date:
18 December 2020
13 -
15 April 2011
Stockholm, Sweden
Published date:
18 December 2020