Results of severe fuel damage experiment QUENCH-14 with advanced rod cladding M5®. (KIT Scientific Reports ; 7549)

Beschreibung

The QUENCH experiments are to investigate the hydrogen release resulting from the water injection into an uncovered core of a Light Water Reactor as well as the high-temperature behavior of core materials. The QUENCH-14 experiment investigated the effect of M5® cladding material on bundle oxidation and core reflood, in comparison with the tests QUENCH-06 that used standard Zircaloy-4 and QUENCH-12 that used VVER E110-claddings.
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Juri Stuckert

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bundle test quenching fuel element cladding oxidation reflood severe accident management

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