19 -
23 May 2024
Lucca, Italy
Published date:
29 April 2024
22 -
26 May 2023
Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM
Published date:
17 May 2023
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 to collect,...
Published date:
25 January 2024
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Innovative Fuel Elements (EGIFE) conducts joint and comparative studies to identify te...
Published date:
8 February 2024
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Fuel Recycling and Waste Technology (EGFRW) focuses on the separation processes releva...
Published date:
25 January 2024
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS) studies the needs associated with the transitio...
Published date:
25 January 2024
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 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 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:
5 March 2024
27 May 2024
INFN Laboratori Nazionali di Frascati, Frascati, Italy
Published date:
16 April 2024
The Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) studies advanced nuclear fuel cycles, including fuel cycle scenarios, innovative fuels and materials, separation chemistry, waste...
Published date:
8 February 2024
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:
21 December 2023
The Working Party on Nuclear Criticality Safety (WPNCS) deals with technical and scientific issues relevant to criticality safety. Specific areas of interest include (but are not limited to) investig...
Published date:
28 March 2024
The Working Party on Multi-scale Modelling of Fuels and Structural Material for Nuclear Systems (WPMM) was established to deal with the scientific and engineering aspects of fuels and structural mate...
Published date:
6 December 2023
Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM) addresses materials science aspects of nuclea...
Published date:
1 June 2023
The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countrie...
Published date:
28 August 2023
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
The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.
Published date:
14 June 2023
Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 2023.
Published date:
24 July 2023
The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:
- oxide-carbide fuel (U-Pu-O-C, released Decemb...
Published date:
23 February 2023
Published date:
2 August 2023
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
TCOFF Phases
First Phase (2017-2020)
The Thermodynamic Characterisation of Fuel Debris and Fission Products ...
Published date:
6 October 2023
High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...
Published date:
19 July 2023
NEA/NSC/R(2022)1
There is significant international interest in the effects of temperature on criticality safety evaluations. Improved access to nuclear data, notably thermal scattering data S(α,β) for hydrogen in ic...
Published date:
2 November 2023
22 -
23 June 2023
IRSN, Fontenay-aux-Roses, France
In the early decades of nuclear reactor development, many countries built and operated zero-power facilities in which many different critical arrangements of materials were studied. These flexible ex...
Published date:
6 June 2023
The NEA workshop gathered experts to discuss the challenges and opportunities related to the demise of zero power reactors.
Published date:
4 July 2023
6 September 2023 -
27 October 2023
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
Published date:
5 September 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:
4 October 2023
NEA/NSC/R(2023)9
The Expert Group on Innovative Structural Materials (EGISM) was created in 2008 under the auspices of the Nuclear Science Committee’s (NSC) Working Party on Scientific Issues of the Fuel Cycle (WPFC)...
Published date:
12 March 2024
The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....
Published date:
18 January 2024
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
Published date:
19 June 2023
NEA/NSC/R(2021)3
Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...
Published date:
17 February 2023
Knowledge of basic nuclear physics data is essential for the modelling and safe operation of all types of nuclear facilities. The de facto international standard format, Evaluated Nuclear Data File 6...
Published date:
22 September 2023
28 -
31 May 2024
INFN Laboratori Nazionali di Frascati, Frascati, Italy
Published date:
18 July 2023
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:
10 January 2024
31 March 2025 -
3 April 2025
Madrid, Spain
The OECD Nuclear Energy Agency (NEA) and CIEMAT are co-organising the Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). The workshop will be held in Mad...
Published date:
29 April 2024
JEFF Nuclear Data Week promotes co-operation between experimentalists, evaluators, producers and end-users of nuclear data.
Published date:
19 December 2023
22 April 2024 -
22 May 2024
Online training & in-person event on 20-22 May 2024 in Lucca, Italy
Published date:
21 December 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:
21 November 2023
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
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
Image: QUENCH facility at KIT. Court. KIT.
The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...
Published date:
17 May 2023
More than 20 international experts gathered for the second meeting of the third phase of the TAF-ID project.
Published date:
21 December 2023
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
PWR MOX/UO2 Core Transient Benchmark
Published date:
7 December 2022
Established to help fulfil the objectives of the Agency and the Nuclear Science Committee (NSC), the NSC Programme Review Group (PRG) formulates recommendations based on best practices to optimise ac...
Published date:
19 March 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:
6 December 2023
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 NEA launched the Nuclear Education, Skills and Technology (NEST) Framework in partnership with its member countries to help address important gaps in nuclear skills capacity building, knowledge t...
Published date:
13 September 2023
The 2021 edition can be downloaded online.
Published date:
22 November 2022