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

Experts met on 17-19 September for the 25^th WGFS annual meeting in Paris. 

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 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 Working Group on Fuel Cycle Safety (WGFCS), which is part of the Committee on the Safety of Nuclear Installation (CSNI) of the Nuclear Energy Agency (NEA), held an international workshop on devel...

Rising international interest in increasing fuel burnup limits and fuel cycle length may require fuel enrichment above 5% and high reactivity/high suppression core designs. Based on this interest in ...

The tsunami that followed the Great East Japan earthquake on 11 March 2011 led to beyond design-basis accidents at Units 1, 2 and 3 of the Fukushima Daiichi Nuclear Power Plant even though they had b...

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

WPFC member gathered to discuss current and future activities.

New NEA nuclear safety joint project 'Pool during Loss of Cooling Accident' (POLCA) launched during a meeting of 40 international experts on 9-10 April, 2024. (Photo: Large scale MIDI facility at IRS...

The fourth FACE meeting brought together experts to Cologne, Germany.

Heavy liquid metals such as lead or lead-bismuth have been proposed and investigated as coolants for fast reactors since the 1950s. More recently, there has been renewed interest worldwide in the use...

More than 20 international experts gathered for the second meeting of the third phase of the TAF-ID project.

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

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...

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...

Expert groups on structural and fuel materials meet to advance materials science activities

Thermodynamic databases and accident prevention

International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.

Two new reports from the WGFS highlight the latest developments in RIA research.

Following the recommendations from the technical workshop on “Nuclear Fuel Behaviour during Reactivity-Initiated Accidents” organised by the Nuclear Energy Agency (NEA) in September 2009, a first ben...

Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) meeting, 8 June 2021.

Understanding fuel performance is a key condition for successful reactor operation. Scientific knowledge in this domain was conceived by experimental tests encoded into software routines to ensure ac...

The nuclear fuel cycle is the chain of processes whereby nuclear fuel is prepared and managed before and after its use in a reactor.

Uranium is the raw material used for nuclear energy generation. It is mined and further processed to make up the highly engineered fuel that is used in nuclear reactors.

NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...

The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel component...

Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...

Development of innovative fuels such as homogeneous and heterogeneous fuels, ADS fuels, and oxide, metal, nitride and carbide fuels is an important stage in the implementation process of advanced nuc...

This publication provides an introduction to minor actinide nuclear properties and discusses some of the arguments in favour of minor actinide recycling, as well as the potential role of thermal reac...

Materials performance is critical to the safe and economic operation of any nuclear system. As the international community pursues the development of Generation IV reactor concepts and accelerator-dr...