Hydrogen embrittlement of unirradiated steels for nuclear reactor pressure vessels
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference23 articles.
1. Hydrogen effects in an irradiated 1 % Cr, % Mo pwr pressure vessel steel
2. Radiolytic problems in water reactors
3. Hydrogen embrittlement of steel pressure vessels in pressurised water reactor systems
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1. In-situ investigations of hydrogen influenced crack initiation and propagation under tensile and low cycle fatigue loadings in RPV steel;Journal of Nuclear Materials;2020-02
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3. Effect of hydrogen on mechanical properties of heat affected zone of a reactor pressure vessel steel grade;Welding in the World;2016-03-18
4. Influence of hydrogen on the toughness of irradiated reactor pressure vessel steels;Journal of Nuclear Materials;2006-12
5. Small-angle neutron scattering study on the effect of hydrogen in irradiated reactor pressure vessel steels;Journal of Nuclear Materials;2005-01
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