1 -
6 October 2023
Sendai International Center, Miyagi, Japan
The 12th International Conference on Nuclear Criticality Safety (ICNC) will be held in Sendai, Japan on 1-6 October 2023. Twenty years after the last conference in Japan, which was held in Tokai-mura...
Published date:
13 December 2022
22 -
26 May 2023
Bologna, Italy
Published date:
2 August 2022
20 -
24 February 2023
NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France) with a remote access option
Published date:
30 January 2023
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:
3 February 2023
The EGMUP Task Force on artificial intelligence and machine learning will design benchmark specifications to evaluate the performance of AI/ML in multi-physics modeling and simulation of reactor syst...
Published date:
1 February 2023
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:
31 January 2023
NEA/NSC/R(2021)1
This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...
Published date:
30 January 2023
The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...
Published date:
17 January 2023
Published date:
17 January 2023
Courses were held in November 2022 in paris, France.
Published date:
14 December 2022
The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
Published date:
13 December 2022
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
TCOFF Phases
First Phase (2017-2020)
The TCOFF project established a framework for the exchange of technical...
Published date:
7 December 2022
PWR MOX/UO2 Core Transient Benchmark
Published date:
7 December 2022
NEA/NSC/R(2022)3
The NEA Expert Group on Used Nuclear Fuel criticality (EGUNF) organised a Phase IIB benchmark to re-examine code and nuclear data performance for BWR lattice calculations and focus on the depletion m...
Published date:
30 November 2022
NEA/NSC/R(2022)4
Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) was established to co-ordinate scientific activities related to ad...
Published date:
29 November 2022
MeshTal Viewer user manual
Published date:
25 November 2022
JANIS (Java-based nuclear information software) is an application designed to facilitate the visualisation and manipulation of nuclear data. JANIS will be helpful to engineers and physicists who use ...
Published date:
24 November 2022
The 2021 edition can be downloaded online.
Published date:
22 November 2022
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Reactor Coolants and Components Technology (EGCoCoT) undertakes activities with the go...
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
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...
Published date:
10 November 2022
The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...
Published date:
10 November 2022
The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
Published date:
10 November 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
High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists consists in a multi-staged code-to-code-to-data thermal hydraulics code validation...
Published date:
9 November 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:
19 October 2022
The mission of the Expert Group of Shielding aspects of Accelerators, Targets and Irradiation Facilities (SATIF) has been completed. Its work initiated the SATIF workshops which keep on serving as in...
Published date:
19 October 2022
The expert group primarily acted as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance.
Published date:
18 October 2022
View of Dragon Reactor. Photo: AEA Technology.
In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...
Published date:
14 October 2022
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
NEA/NSC/R(2020)4
Advanced nuclear fuel cycles to improve the safety, sustainability and economics of nuclear energy are being investigated worldwide. Partitioning and transmutation (P&T) is one of the candidate techn...
Published date:
11 October 2022
The event gathered 129 participants from 75 international institutions.
Published date:
6 October 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
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
As governments around the world are committing to reaching net zero emissions by 2050, many countries are looking at the role hydrogen can play in mitigating climate change. This page provides more i...
Published date:
16 September 2022
The first QUENCH-ATF joint project test was successfully completed by the KIT team on 17 July 2022.
Published date:
5 August 2022
The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.
Published date:
4 August 2022
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 Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) and its expert groups co-ordinate benchmark activities on Reactor Single- and Multi-Physics. The benchmark ac...
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 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:
2 August 2022
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:
2 August 2022
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:
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
Over its 25 years of existence, the working party has contributed many topics and has led advances in criticality safety studies.
Published date:
28 July 2022
