WPNCS bi-annual event brought together 80 experts from 17 member countries.
Published date:
7 February 2022
The expert group is responsible for managing the activities related to the High Priority Request List (HPRL) for nuclear data, in particular for guaranteeing that the entries are up-to-date and well-...
Published date:
20 September 2022
The expert group was established to develop a nuclear data structure definition that can meet the needs of a broad set of nuclear data users and providers.
Published date:
20 September 2022
The objectives of the expert group are to assess the accuracy and calculation time of the various first principle tools applied in the assessment of the properties of the nuclear materials; assess th...
Published date:
5 March 2020
The main objectives of this expert group are to assess the limitations of the NRT-dpa standard, in the light of both atomistic simulations and known experimental discrepancies; and to revisit the NRT...
Published date:
5 March 2020
The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.
Published date:
26 July 2021
The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors. There are in addition incentives to better utilise fuel by increasing the b...
Published date:
19 July 1995
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
This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...
Published date:
2 August 2022
Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark
Published date:
2 August 2022
NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark
Published date:
2 August 2022
A number of tests with detail well documented neutronics and thermal-hydraulics measurements data have been performed at the Rostov Unit 2 (Rostov-2) nuclear power plant (NPP). The reactor type is a ...
Published date:
2 August 2022
The overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...
Published date:
2 August 2022
The NEA Data Bank organised a PENELOPE training course at the University of Barcelona in Spain on 11-15 July 2022
Published date:
1 August 2022
TVA Watts Bar Unit 1 Multi-Physics Benchmark
Published date:
19 July 2022
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
Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) Benchmark
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
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...
Published date:
19 July 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
The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...
Published date:
19 July 2022
30 May 2022 -
3 June 2022
Conference Center Hotel Aquabella, Aix-en-Provence, France (in-person meeting)
Published date:
29 March 2022
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
27 June 2022 -
1 July 2022
OECD headquarters, Paris XVI
Published date:
1 June 2022
Nuclear Data Sensitivity Tool (NDaST), aims to provide rapid feedback on the effect of changes to nuclear data on integral benchmarks.
Published date:
17 May 2022
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experime...
Published date:
25 April 2022
Collected sources of primary documentation for reactor physics benchmarks.
Published date:
14 April 2022
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:
23 March 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
21 -
25 February 2022
ZOOM virtual meeting
Published date:
7 February 2022
The webinar "Research and international dialogue in technology nuclear power - What role for Italy?", was held on 17- 18 November 2021.
Published date:
14 December 2021
Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) meeting, 8 June 2021.
Published date:
30 June 2021
Preparatory meeting for Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)...
Published date:
27 May 2021
NEA Thermodynamics of Advanced Fuels International Database updates
Published date:
25 January 2021
New NEA task force on partitioning and transmutation kicks off
Published date:
27 January 2021
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) workshops, 7-15 December 2020.
Published date:
17 December 2020
Nuclear data refers to the probabilities, statistics and measurements of the physical interactions associated with atomic particles.
Published date:
16 December 2019
New NEA reports on nuclear data evaluation
Published date:
5 August 2020
The expert group dealt with the activities associated with the certification of experimental data and benchmark models along with establishing the processes and procedures for using the data and benc...
Published date:
23 November 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 NEA Expert Group on Innovative Structural Materials (EGISM) organised a workshop on 19-21 October 2021 together with the Spanish Center for Energy, Environmental and Technological Research (CIEMA...
Published date:
3 November 2021
20 -
23 September 2022
Facility for Rare Isotope Beams at Michigan State University, East Lansing, Michigan (USA)
The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...
Published date:
2 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
Helium-cooled very high-temperature gas reactors are highlighted as a key technology with the potential to improve the competitiveness of nuclear energy within the Generation IV International Forum (...
Published date:
20 September 2021
For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.
Published date:
8 September 2021
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
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
The Technical Review Group (TRG) for the International Assay Data of Spent Nuclear Fuel Database (SFCOMPO) lies under the direction of the Working Party on Nuclear Criticality Safety (WPNCS).
Published date:
13 April 2021
MeshTal Viewer is a Java based software which can read mesh tallies output formats of several neutron transport codes and display them graphically.
Published date:
2 October 2020
Published date:
21 June 2016