Microstructure and mechanical behavior of ODS and non-ODS Fe–14Cr model alloys produced by spark plasma sintering
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference20 articles.
1. Influence of particle dispersions on the high-temperature strength of ferritic alloys
2. Structural materials challenges for advanced reactor systems
3. Structural materials issues for the next generation fission reactors
4. Recent Developments in Irradiation-Resistant Steels
5. Review on the EFDA work programme on nano-structured ODS RAF steels
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