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Published in 2021 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2021.108559
Abstract: Abstract In the existing Probabilistic Safety Assessment (PSA) model, all the Steam Generator Tube Rupture (SGTR) sequences have been assumed to have identical fission product release characteristics without considering the sequences of no source term…
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Keywords:
steam generator;
evaluation;
sgtr;
source ... See more keywords