The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiments Evaluation Project (IRPhEP) Technical Review Groups, and the Shielding Int...

Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, an...

Publié chaque année, le Rapport annuel de l’AEN présente un aperçu des activités et publications de l’AEN pour une année donnée, ainsi que les derniers développements du secteur de l’énergie nucléair...

Published every year, the NEA Annual report includes an overview of NEA's activities and publications produced during the year, as well as the latest developments in nuclear energy sector around the ...

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...

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...

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-...

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...

The International School on Simulation of Nuclear Reactor Systems (SINUS) provides hybrid, hands-on-training encompassing multiphysics modelling and simulation (M&S) and associated validation, verifi...

FIDES-II member assembled at the Japan Atomic Energy Agency (JAEA) in Mito, Japan.

The benchmark will predict the Critical Heat Flux (CHF).

The NEA hosted the 16th edition of information exchange meetings on actinide and fission product partitioning and transmutation (16IEMPT).

The NEA and IAEA jointly organised an international workshop in Vienna, Austria, on 2-6 October 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 ...

In November 2023, the NEA Data Bank held two beginner level courses in Paris, France.

The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.

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...

Recent performance breakthroughs in Artificial Intelligence (AI) and Machine Learning (ML) have led to unprecedented interest in AI/ML among nuclear engineers. However, the lack of dedicated benchmar...

Experts from 16 countries met on 13-15 September for the 24^th annual Working Group on Fuel Safety GFS meeting in Paris. 

The NEA is organising the 16^th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT) on 24-27 October 2023. The meeting will be held at the NEA offices...

Encouraging greater cohesion of social sciences and STEM to push the nuclear sector forward

The NEA Global Forum on Nuclear Education, Science Technology and Policy (the NEA Global Forum) held a coun...

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 ...

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...

The Global Forum on Nuclear Education, Science, Technology and Policy acts as an inclusive network of experts in the nuclear energy sector, primarily from academia, focused on enabling the generation...

The 12th International Conference on Nuclear Criticality Safety (ICNC) was held in Sendai, Japan, on 1-6 October 2023. Twenty years after the last conference in Japan, which was held in Tokai-mura as...

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...

The Task Force on Dose Rate Calculations for Irradiated Fuel Assembly was launched in 2015 to assess code predictions of dose rates from bare spent fuel assemblies and to benchmark multiple codes and...

The goal of the Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) Subgroup on Experimental Needs for Criticality Safety Purposes (SG-5) was to highlight the needs of int...

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...

Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.

Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

The NEA Working Party on Nuclear Criticality Safety (WPNCS) held its bi-annual meetings in June 2023

Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 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...

TCOFF-2 members discuss future activities.

The NEA workshop gathered experts to discuss the challenges and opportunities related to the demise of zero power reactors.

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...

10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.

Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.

The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.

The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.

WPFM held meetings on 23-25 May 2023.

The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

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 ...

The NEA thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H), supervised by the Expert Group on Reactor Core Thermal-Hydraulics and Mechanic...

The annual Benchmark Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted by the Italian National Agency for New Technologies, Energy and Sus...

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...

The NEA organised the first International School on Simulation of Nuclear Reactor Systems (SINUS) on the topic of Reactor single- and multi-physics simulations based on Light Water Reactor (LWR) Unce...

The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.

Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.

International Fuel Performance Experiments (IFPE) is a data collection of nuclear fuel performance experiments for the purpose of code development and validation.

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 ...

Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...

EGPRS Task Force members met on 3 April 2023.

This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...