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

Please note that this report was initially published in November 2022 (NEA/NSC/R(2022)3) under erroneous benchmark number IIB; in this updated version (NEA/NSC/R(2022)3/CORR) this has been corrected ...

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...

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 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...

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

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...

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...

TCOFF-2 members discuss future activities.

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...

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

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.

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. 

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 ...

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 ...

Sustained performance of nuclear technology depends on access to a talented and well-qualified workforce, thus it is important to ensure that adequate infrastructures exist for education and training...

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 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 nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.

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...

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...

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 ...

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 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.