Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions

摘要

In 1986, a Working Group of the Committee on the Safety of Nuclear Installations (CSNI) issued a State-of-the-Art Report (SOAR) on pressurised water reactor fuel behaviour in design basis accident (DBA) conditions. The current State-of-the-Art Report on fuel behaviour in LOCA conditions is an updated version that describes phenomena of importance in the loss-of-coolant-accident (LOCA). New information has been produced concerning these phenomena. Older cladding materials have been replaced by newer alloys that may behave differently under postulated accident conditions. There is also a clear need to include discussions on accident issues for other water cooled reactor types. This is especially important now when the Eastern European countries have joined the discussion on nuclear safety issues.