Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250–450°C

Author:

Alamo A,Horsten M,Averty X,Materna-Morris E.I,Rieth M,Brachet J.C

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference12 articles.

1. Low-activation ferritic and martensitic steels for fusion application

2. Optimum alloy compositions in reduced-activation martensitic 9Cr steels for fusion reactor

3. Physical metallurgy and mechanical behaviour of FeCrWTaV low activation martensitic steels: Effects of chemical composition

4. R.L. Klueh, D.J. Alexander, in: Proceedings of the 18th International Symposium, Effects of Radiation on Materials: ASTM STP, vol. 1325, 1999, p. 911

5. R.L. Klueh, in: Proceedings of the IEA Working Group Meeting on Ferritic-Martensitic Steels, Report ORNL/M-3777, Sun Valley, USA, June 1994

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