3-D Radiation Transport benchmarks dealt with scientific issues in the field of deterministic and stochastic methods and computer codes relative to three dimensional (3-D) radiation transport.
Published date:
30 September 2020
NEA/NSC/R(2019)1
The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...
Published date:
18 January 2019
WPRS organised annual benchmarks workshop.
Published date:
12 June 2024
An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.
Published date:
2 August 2022
NEA/NSC/R(2015)9
Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...
Published date:
5 November 2015
The Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors (LWRs) is an international high-visibility benchmark for unce...
Published date:
30 September 2020
10 -
11 May 2007
Paris, France
Published date:
18 December 2020
1 -
3 June 2016
Villigen, Switzerland
Published date:
18 December 2020
10 -
12 May 2017
Erlangen, Germany
Published date:
18 December 2020
16 -
17 May 2018
Lucca, Italy
Published date:
18 December 2020
13 -
17 May 2019
Oak Ridge, United States
Published date:
18 December 2020
2 -
4 April 2008
Garching, Germany
Published date:
18 December 2020
29 April 2009 -
1 May 2009
University Park/State College, Pennsylvania, United States
Published date:
18 December 2020
13 -
15 April 2010
Pisa, Italy
Published date:
18 December 2020
13 -
15 April 2011
Stockholm, Sweden
Published date:
18 December 2020
9 -
11 May 2012
Karlsruhe, Germany
Published date:
18 December 2020
14 -
16 May 2014
Garching, Germany
Published date:
21 December 2020
20 -
22 May 2015
Madrid, Spain
Published date:
18 December 2020
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
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
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
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
Published date:
13 June 2023
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) workshops, 7-15 December 2020.
Published date:
17 December 2020
Published date:
16 May 2013
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
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
Published date:
23 February 2016
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
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
Published date:
12 October 2020
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
The event gathered 129 participants from 75 international institutions.
Published date:
6 October 2022
WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.
Published date:
9 June 2022
EGPRS Task Force members met on 3 April 2023.
Published date:
7 April 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
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:
11 December 2024
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:
11 December 2024
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-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
The benchmark will predict the Critical Heat Flux (CHF).
Published date:
22 November 2023
10 -
13 June 2025
NEA, Paris, France
Date: 10-13 June 2025
Place: OECD/NEA headquarters
46, Quai Alphonse Le Gallo
92100 Boulogne-Billancourt (Paris) - FRANCE
Minimum enrollment: 8 participants
Maximum enrollment: 22 participan...
Published date:
17 December 2024
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 Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
Published date:
24 April 2023
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
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
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:
14 June 2024
