Tensile properties of ODS-14%Cr ferritic alloy irradiated in a spallation environment
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference13 articles.
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1. Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review;Journal of Physics: Energy;2022-07-01
2. Investigation of mechanical property changes in He2+ ion irradiated MA957 through nanoindentation and in situ micro-tensile testing;Journal of Nuclear Materials;2021-04
3. Optimization of zirconium and yttrium content in 17Cr ferritic ODS steel through Taguchi analysis;Materials Today: Proceedings;2021
4. Prediction of mechanical properties for ferritic ODS steel using the nanoindentation test;RECENT TRENDS IN MANUFACTURING TECHNOLOGIES, MATERIALS PROCESSING, AND TESTING;2021
5. Synthesis and Characterization of 17 Cr Ferritic ODS Steel Developed Through Vacuum Hot Pressing;Lecture Notes in Mechanical Engineering;2020-09-27
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