Development of high-chromium steel for the sodium-cooled fast reactor in Japan and creep–fatigue assessment of the steel-Reference-Cited by-同舟云学术

Development of high-chromium steel for the sodium-cooled fast reactor in Japan and creep–fatigue assessment of the steel

Published:2008-06 Issue:6 Volume:85 Page:352-359
ISSN:0308-0161
Container-title:International Journal of Pressure Vessels and Piping
language:en
Short-container-title:International Journal of Pressure Vessels and Piping

Author:

Wakai Takashi,Sukekawa Masayuki,Date Shingo,Asayama Tai,Aoto Kazumi,Kubo Shigenobu

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference7 articles.

1. PNC (Power Reactor and Nuclear Fuel Development Corporation). Structural design guide for class 1 components of prototype fast breeder reactor for elevated temperature service, 1984.

2. Fujita T. Advances in 9-12Cr heat resistant steels for power plants. In: Third EPRI conference on advanced materials technology for fossil plants, 2001.

3. Creep-fatigue evaluation of normalized and tempered modified 9Cr-1Mo;Aoto;Nucl Eng Des,1994

4. Wada Y, et al. New concept on ductility exhaustion considering creep-fatigue failure mechanism of type 304 SS. In: Proceedings of the 31st symposium Str. Mater. High Temp., 1993 (in Japanese).

5. Wakai T, et al. Present status of development of high chromium steel for Japanese FBR components. Nucl Eng Des, to be published, 2007.

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