Void swelling in a 9Cr ferritic/martensitic steel irradiated with energetic Ne-ions at elevated temperatures
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference27 articles.
1. Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences
2. Mechanical properties of modified 9Cr–1Mo (T91) irradiated at ⩽300 °C in SINQ Target-3
3. Small punch tests on martensitic/ferritic steels F82H, T91 and Optimax-A irradiated in SINQ Target-3
4. Effect of implanted helium on tensile properties and hardness of 9% Cr martensitic stainless steels
5. Microstructural analysis of 9% Cr martensitic steels containing 0.5 at.% helium
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