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Published in 2019 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2018.10.002
Abstract: Abstract The corium containing stainless steel, partially oxidized zirconium cladding and fuel materials in the lower plenum may separate into immiscible liquids at high temperatures that influence the heat flux into vessel during in-vessel melt…
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Keywords:
corium;
heat;
transfer corium;
lower plenum ... See more keywords