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on 1/25/22 at 4:48 PM
In 1986, a working group of the NEA Committee on the Safety of Nuclear Installations issued a state-of-the-art report on water reactor fuel behaviour in design-basis accident (DBA) conditions. The report was limited to the oxidation, embrittlement and deformation of pressurised water reactor (PWR) fuel in a loss-of-coolant accident (LOCA).
Since then, a considerable worldwide effort has been expended in experimental and numerical modelling of PWR and boiling water reactor (BWR) fuel behavior under accident conditions, in particular for high burn-up fuel, which has allowed the updating of the 1986 report and expansion of its scope to include other types of DBAs, such as reactivity initiated accidents (RIAs). The Working Group on Fuel Safety (WGFS) issued a first update covering nuclear fuel behaviour under LOCA conditions in 2009. The present report addresses nuclear fuel behaviour under RIA conditions.
