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Published in 2019 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2018.12.019
Abstract: Abstract The RELAP5/MOD3.3 code was used to simulate a Main Steam Line Break (MSLB) Loss of Coolant Accident (LOCA) on a Generation III type Reactor with passive safety features. The MSLB is a hypothetical multi-failure…
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Keywords:
large break;
break loca;
uncertainty;
break ... See more keywords