Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan
2007 Annual Meeting
Session ID : N17
Conference information
Technological development of a nuclear fuel cycle based on nitride fuel and pyrochemical reprocessing
(II)Application of indentation creep method to uranium nitride
*Masahide Takano, Mitsuo Akabori, Yasuo Arai, Kazuo Minato
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Keywords: Nitride fuel, Uranium nitride, Thermal creep, Indentation, Small specimen
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[in Japanese]
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© 2007 Atomic Energy Society of Japan
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