T
Takashi Nozawa
Researcher at Japan Atomic Energy Agency
Publications - 78
Citations - 3663
Takashi Nozawa is an academic researcher from Japan Atomic Energy Agency. The author has contributed to research in topics: Silicon carbide & Ultimate tensile strength. The author has an hindex of 23, co-authored 62 publications receiving 3125 citations. Previous affiliations of Takashi Nozawa include Oak Ridge National Laboratory.
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Handbook of SiC properties for fuel performance modeling
TL;DR: In this paper, a compilation of non-irradiated and irradiated properties of SiC are provided and reviewed and analyzed in terms of application to TRISO fuels, specifically in the high-temperature irradiation regime.
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Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects
Yutai Katoh,Kazumi Ozawa,Chunghao Shih,Takashi Nozawa,Robert J. Shinavski,Akira Hasegawa,Lance Lewis Snead +6 more
TL;DR: In this article, a summary of the properties of SiC/SiC composites with chemically vapor-infiltrated (CVI) SiC matrices is presented.
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Current status and recent research achievements in SiC/SiC composites
Yutai Katoh,Lance Lewis Snead,Charles H. Henager,Takashi Nozawa,Tatsuya Hinoki,Aljaž Iveković,Saša Novak,S.M. González de Vicente +7 more
TL;DR: The silicon carbide fiber-reinforced SiC/SiC composite system for fusion applications has seen a continual evolution from development a fundamental understanding of the material system and its behavior in a hostile irradiation environment to the current effort which is directed at a broad-based program of technology maturation program as mentioned in this paper.
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Silicon carbide composites as fusion power reactor structural materials
Lance Lewis Snead,Takashi Nozawa,Monica Ferraris,Yutai Katoh,Robert J. Shinavski,Mohamed E. Sawan +5 more
TL;DR: The recent progress in the understanding and of basic phenomenon related to the use of SiC and SiC composite in fusion applications will be presented in this article, including both fundamental radiation effects in SiC, and engineering issues such as joining and general materials properties.
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Properties of zirconium carbide for nuclear fuel applications
TL;DR: In this paper, a survey of properties data for Zirconium carbide (ZrC) is provided in support of the current efforts toward fuel performance modeling and providing guidance for future research on ZrC for fuel applications.