Corrosion behavior of ODS steels with several chromium contents in hot nitric acid solutions
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference28 articles.
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4. ODS Ferritic/martensitic alloys for Sodium Fast Reactor fuel pin cladding;Dubuisson;J. Nucl. Mater,2012
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