In situ observation of damage structure in ODS austenitic steel during electron irradiation
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference9 articles.
1. Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials
2. Irradiation creep and swelling from 400 to 600 °C of the oxide dispersion strengthened ferritic alloy MA957
3. Effect of He on void formation and radiation-induced segregation in dual-beam irradiated Fe-Cr-Ni
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