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 nu...
Published date:
12 August 2024
20 -
23 September 2022
Facility for Rare Isotope Beams at Michigan State University, East Lansing, Michigan (USA)
SATIF-15 Workshop participants. Photo: courtesy of the Facility for Rare Isotope Beams (FRIB)
Published date:
6 August 2024
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:
26 July 2024
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
27 May 2024
INFN Laboratori Nazionali di Frascati, Frascati, Italy
Published date:
27 May 2024
19 -
22 November 2024
Paris, France
Dates: 19-22 November 2024
Minimum enrollment: 12 participants
Maximum enrollment: 20 participants
Registration fee: 750 EUR
Registration deadline: 27 September 2024
Contact: hedvig.nahon@oecd-nea.org wit...
Published date:
28 June 2024
2 -
6 December 2024
NEA, Paris, France
Date: 2-6 December 2024
Place: OECD/NEA Headquarters
46, Quai Alphonse Le Gallo
92100 Boulogne-Billancourt (Paris) - FRANCE
Minimum enrollment: 15 participants
Maximum enrollment: 20 parti...
Published date:
26 June 2024
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
WPRS organised annual benchmarks workshop.
Published date:
12 June 2024
19 -
23 May 2024
Lucca, Italy
Published date:
31 May 2024
The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...
Published date:
30 May 2024
Proceedings of the First Specialists' Meeting on Shielding Aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) at Arlington, USA on 28-29 April 1994.
Published date:
6 May 1995
The meetings took place in April 2024 in the United States.
Published date:
25 April 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
27 -
31 May 2024
Online training course
Dates: 27-31 May 2024
Time: 17:00-21:00 (CEST, Paris time)/10:00-14:00 (CDT USA/Mexico)/12:00-16:00 (UTC-3, Argentina)
Minimum enrollment: 12 participants
Maximum enrollment: 15 participants
Registration...
Published date:
19 March 2024
Proceedings of the Second Specialists' Meeting on Shielding Aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) at CERN, Geneva, Switzerland on 12-13 October 1995.
Published date:
4 March 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:
6 December 2023
The benchmark will predict the Critical Heat Flux (CHF).
Published date:
22 November 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 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
14 -
17 November 2023
NEA, Paris, France
Date: 14-17 November 2023
Place: NEA Headquarters
46, Quai Alphonse Le Gallo
92100 Boulogne-Billancourt (Paris) - FRANCE
Minimum enrollment: 12 participants
Maximum enrollment: 20 participants...
Published date:
2 October 2023
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
Published date:
13 June 2023
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
The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.
Published date:
14 June 2023
22 -
26 May 2023
Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM
Published date:
17 May 2023
22 -
26 May 2023
NEA, Paris (France)
Place: OECD/NEA Headquarters in Paris, France
Minimum enrollment required: 12 participants
Course fee: 2300 EUR
Registration closed
The training course will be taught in English.
Participan...
Published date:
17 May 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
5 -
6 June 2023
Oregon State University, Corvallis, Oregon, United States
Published date:
20 April 2023
The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
Published date:
24 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
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.
Published date:
4 March 2020
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.
Published date:
24 February 2021
EGPRS Task Force members met on 3 April 2023.
Published date:
7 April 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
Understanding fuel performance is a key condition for successful reactor operation. Scientific knowledge in this domain was conceived by experimental tests encoded into software routines to ensure ac...
Published date:
10 December 2020
Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.
Published date:
2 December 2019
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
Published date:
23 February 2016
Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...
Published date:
10 December 2020
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
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
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
Published date:
6 December 2017
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
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
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(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