The NEA is organising the 16th 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 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 long-term hazard of radioactive waste arising from nuclear energy production is a matter of continued discussion and public concern in many countries. Through partitioning and transmutation (P&T)...
The objective of the OECD/NEA Information Exchange Programme on Actinide and Fission Product Partitioning and Transmutation (P&T), established in 1989, is to enhance the value of basic research in th...
The Ad hoc Expert Group on Trends in the Nuclear Fuel Cycle (TNFC) was set up to investigate trends in the latest progress and the future trajectories in the nuclear fuel cycle.
This study analyses a range of advanced nuclear fuel cycle options from the perspective of their effect on radioactive waste management policies. It presents various fuel cycle options which illustra...
The optimisation of the nuclear fuel cycle is a key issue for the sustainability of nuclear energy. This book presents the papers from a workshop which investigated alternative nuclear energy futures...
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...
Cabri Reactor (Commissariat à l’énergie atomique et aux énergies alternatives)
The Cabri International Project (CIP) began in March 2000 to study the behaviour of nuclear fuel rods and cladding durin...
Cette étude analyse différents cycles du combustible nucléaire avancés du point de vue de leur impact sur la gestion des déchets radioactifs. Elle examine divers cycles et illustre les différences en...
Experts from 16 countries met on 13-15 September for the 24th annual Working Group on Fuel Safety GFS meeting in Paris.
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...
WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Fuel Materials (EGFM) focuses on materials science aspects of...
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...
Challenges related to extended storage are topical in most countries with mature nuclear programmes. Effort to address this issue is ongoing in individual countries. Available knowledge from member c...
Some 100 international experts convened in New Jersey, U.S for the Workshop on Extended Storage and Transportation of Spent Fuel and Radioactive Waste from Current and Future Reactor Technologies.