Tensile stress–strain and work hardening behaviour of P9 steel for wrapper application in sodium cooled fast reactors-Reference-Cited by-同舟云学术

Tensile stress–strain and work hardening behaviour of P9 steel for wrapper application in sodium cooled fast reactors

Published:2012-01 Issue:1-3 Volume:420 Page:583-590
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Christopher J.,Choudhary B.K.,Isaac Samuel E.,Mathew M.D.,Jayakumar T.

Publisher

Elsevier BV

Subject

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

Reference43 articles.

1. Ferritic Steels for Fast Reactor Steam Generators;Wood,1977

2. Ferritic Steels for High Temperature Applications;Sanderson,1981

3. Ferritic Alloys for Use in Nuclear Energy Technologies;Sikka,1984

4. Ferritic Steels for Fast Reactor Steam Generators;Cane,1977

5. Badev Raj, in: Baldev Raj, B.K. Choudhary, K. Velusamy (Eds.), Pressure Vessels and Piping: Codes ,Standards, Design and Analysis, Narosa Publishing House, New Delhi, 2009, pp. 1–32.

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