The 11th NEA Expert Group on Reactor Coolants and Components Technology (EGCoCoT) meeting was held in Paris on 22-23 April 2025.

The project held Nuclear Data Week to discuss progress of the ongoing activities.

Project members met in France and online to discuss the ongoing and future activities.

https://www.oecd-nea.org/tools/ierequest/start/package/NEA-1939%2501The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for more than 100 reactor shielding, ...

The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP), International Reactor Physics Experiments Evaluation Project (IRPhEP), International Assay Data of Spent Nuclear Fuel D...

Efforts to enhance the safety, sustainability and economic efficiency of nuclear energy are driving international research into advanced nuclear fuel cycles. A key component of these efforts is parti...

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...

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 Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...

The OECD Nuclear Energy Agency (NEA) and Ciemat co-organised the Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7), with the support of industry, Newcleo...

NEA expert group discusses advanced fuel cycle scenarios

International experts discussed plans for an upcoming workshop.

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

The NEA Global Forum on Nuclear Education, Science, Technology and Policy (the Global Forum on Nuclear Education) is a framework for sustained co-operation and for enabling a long-term dialogue among...

The NEA Working Party on Nuclear Criticality Safety discussed ongoing and future activities.

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...

This web page is intended for the description of the nuclear fuel cycle codes that have been used in the recent activities of the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS), under the gui...

NMB4.0 is designed to provide flexibility and an all-in-one packaged nuclear fuel cycle simulation for users as open code. Various ideas have been implemented to improve user-friendliness. The main t...

TR_EVOL (Transition Evolution code) fuel cycle simulator is a tool dedicated to the study of mass balances of advanced transition electronuclear scenarios.

The Advanced Nuclear Cycle Code, ANICCA, is a nuclear fuel cycle simulation code (NFCSC) that has been developed by SCK-CEN as a flexible tool for nuclear fuel cycle studies. ANICCA is able to simula...

Once irradiated or “spent” nuclear fuel is unloaded from a reactor it is usually stored at the reactor site for between five and ten years. It is then ready for long-term storage or for reprocessing ...

Several applications of interest in nuclear criticality safety involve random media, which are media where the geometrical and/or material properties can only be described by assigning some probabili...

The JEFF Nuclear Data Week took place on 25-29 November 2024.

Under the guidance of the Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor ph...

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...

NEA released the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook which contains criticality safety benchmark specifications

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 ...

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...

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...

Members of the NEA joint project Thermodynamics of Advanced Fuels - International Database (TAF-ID) met on 23-25 October 2024.

The Serpent-2 software is a three-dimensional continuous-energy neutron and photon transport code, developed at the Technical Research Centre of Finland (VTT) (Leppänen, 2015), and is one of the most...

TCOFF-2 members met to discus the ongoing activities.

Under the auspices of the Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Reactor Systems (WPRS) has been established to study reactor physics, ...

The NEA Working Party on Nuclear Criticality Safety (WPNCS) and its subgroups held their annual plenary meetings.

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...

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...

SFCOMPO 2.0 (Spent Fuel Isotopic Composition) is a relational database designed to facilitate the search and visualisation of experimental assay data of spent nuclear fuel.

The NEA delegation travelled to Bulgaria to take part in “Sustainable Nuclear Innovations.”

International benchmark of solvent extraction codes and process modelling applied to hydro-processes focuses on the modelling of PUREX (TBP-based extractions) systems with uranium and nitric acid as ...