The Working Party on Scientific Issues of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nuclear power systems.

The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...

DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...

Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...

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...

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 ...

Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of present and future nuclear ...

The expert group conducts joint and comparative studies to identify technical issues and support the development of innovative fuels that can be implemented in advanced nuclear fuel cycles.

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

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...