Post irradiation tensile and fatigue behavior of austenitic PCA stainless steels irradiated in HFIR
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Effect of Radiation on Structural Materials;Martin,1967
2. Irradiation Effects in Structural Alloys for Thermal and Fast Reactors;Bloom,1969
3. A possible solution of the problem of helium embrittlement
4. Modification of the grain boundary microstructure of the austenitic PCA stainless steel to improve helium embrittlement resistance
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2. Bend-fatigue properties of JPCA and Alloy800H specimens irradiated in a spallation environment;Journal of Nuclear Materials;2014-07
3. Tensile mechanical properties of a stainless steel irradiated up to 19dpa in the Swiss spallation neutron source;Journal of Nuclear Materials;2012-12
4. Material Performance in Lead and Lead-bismuth Alloy;Comprehensive Nuclear Materials;2012
5. Bend-fatigue properties of 590 MeV proton irradiated JPCA and 316F SS;Journal of Nuclear Materials;2004-08
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