Information on the evolution of severe LWR fuel element damage obtained in the CORA program
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions
2. Reactor Core Materials Interactions at Very High Temperatures
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