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...

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 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...

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 ...

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 continued evolution of fuel and materials technology, fuel performance, optimisation of operational limits, material ageing, failure limits, etc. requires experimental evidence obtained from test...

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

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.

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 ...