Fuel cladding materials R&D for high burn-up operation

Ukai, Shigeharu*; Inoue, Masaki ; Kimura, Akihiko*

Various oxide dispersion strengthened ferritic steels are reviewed in "Materia Japan" issued by the Japan Institure of Metals. The steels have been developed for sodium cooled fast reactors under the Fast Reactor Cycle Technology Development (FaCT) project and for lead-bismuth and super critical water cooled reactors under the innovative nuclear research and development program. Alloy designing, manufacturing process and mechanical properties of the steels are briefly described.

Language	:	Japanese
Journal	:	Materia
Volume	:	47
Number	:	9
Pages	:	p.450 - 454
Publication Year/Month	:	2008/09
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Paper URL	:	https://ci.nii.ac.jp/naid/10024272577
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Keywords	:	no keyword
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Article of JAEA R&D Review	:
Cooperating Institute	:	京都大学; 北海道大学

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Registration No. : AA20080264
JAEA Abstracts No. : 36001477
Paper Submission No. : 4769

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