Microstructural development of a heavily neutron-irradiated ODS ferritic steel (MA957) at elevated temperature
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference13 articles.
1. Fabrication and Mechanical Properties of Oxide Dispersion Strengthening Ferritic Alloy Canning Tubes for Fast Reactor Fuel Pins
2. E.A. Little, in: Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270 (1996) 739.
3. R&D of oxide dispersion strengthened ferritic martensitic steels for FBR
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