The next annual Benchmarks Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) will be hosted by the Department of Engineering of the University of ...

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

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 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...

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...

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 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-...

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...

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

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.

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 ...

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 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 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 ...

The Expert Group on Reactor Coolants/Components Technology (EGCoCoT), operating under the auspices of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), launched an activity to pr...

The Expert Group on Innovative Fuel Elements (EGIFE), operating under the auspices of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), launched an activity to produce a set of r...

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...

The NEA held a one-day workshop for Radiation Transport Simulation Developers (RTS 2024).

Project members met in France to discuss the ongoing experimental activities.

SATIF community celebrated the 30^th anniversary during the 16^th SATIF workshop hosted on 28-31 May.

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

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 NEA Nuclear Science Committee (NSC) mandated the Expert Group on Multi-Physics Experimental Data, Benchmarks and Validation (EGMPEBV) in 2014 to provide oversight of activities associated with th...

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 ...

The International School on Simulation of Nuclear Reactor Systems took place in Italy. 

WPRS organised annual benchmarks workshop.

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