Sodium fast reactor evaluation: Core materials-Reference-Cited by-同舟云学术

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Sodium fast reactor evaluation: Core materials

Published:2009-07 Issue:2 Volume:392 Page:324-330
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Cheon Jin Sik,Lee Chan Bock,Lee Byoung Oon,Raison J.P.,Mizuno T.,Delage F.,Carmack J.

Publisher

Elsevier BV

Subject

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

Reference32 articles.

1. The Nuclear Fuel of Pressurized Water Reactors and Fast Neutron Reactors;Bailly,1999

2. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure

3. D. Gilbon, in: BNES Proceedings International Conference, Bristol 27–29 October 1987, p. 307.

4. Status of liquid metal cooled fast reactor technology, IAEA-TECDOC-1083, IAEA, 1999.

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