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Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond
https://repo.qst.go.jp/records/49297
https://repo.qst.go.jp/records/492978681f481-35ab-492e-9aa9-55d409de8e67
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-12-04 | |||||
| タイトル | ||||||
| タイトル | Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond | |||||
| 言語 | ||||||
| 言語 | eng | |||||
| 資源タイプ | ||||||
| 資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
| 資源タイプ | journal article | |||||
| アクセス権 | ||||||
| アクセス権 | metadata only access | |||||
| アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
| 著者 |
Nozawa, Takashi
× Nozawa, Takashi× Ozawa, Kazumi× Park, ChangHo× Park, Joon-Soo× Kohyama, Akira× Hasegawa, Akira× Nogami, Shuhei× Hinoki, Tatsuya× Kondo, Sosuke× Yano, Toyohiko× Shibayama, Tamaki× Tsuchiya, Bun× Shikama, Tatsuo× Nagata, Shinji× Tanaka, Teruya× Iwakiri, Hirotomo× Yamamoto, Yasushi× Konishi, Satoshi× Kasada, Ryuta× Kondo, Masatoshi× Kunugi, Tomoaki× Yokomine, Takehiko× Ueki, Yoshitaka× Okubo, Nariaki× Taguchi, Tomitsugu× Tanigawa, Hiroyasu× 野澤 貴史× 小沢 和巳× 朴 昶虎× 田口 富嗣× 谷川 博康 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | The R&D on SiC/SiC composites under the broader approach (BA) activities between Japan and the EU for fusion DEMO developed a fundamental database of mechanical (Task-1) and physical/chemical (Task-2) properties, with a primary target of the application of SiC/SiC composites as functional structure to be used in the dual coolant breeding blanket concept. This paper aims to summarize previous 10-years activities of the R&D of Japan and to provide the key deliverables toward the DEMO design. In Task-1, good creep and fatigue durability were first demonstrated. Besides, in-plane and inter-laminar strength anisotropy maps at elevated temperatures were comprehensively identified. In parallel, the irradiation effects of SiC materials were specifically determined as input parameters of the analytical model to provide for the irradiation-induced residual stresses. In Task-2, the apparent dose-dependence of the radiation-induced electrical conductivity and the indicative radiation-induced electrical degradation was identified by various irradiation sources. In addition, good gas confinement was identified. Furthermore, no accelerated corrosion for duration of 3000 h at below 1173 K was first demonstrated. With these achievements, it is suggested that the in-vessel component technology, e.g., material corrosion database development, activated corrosion product evaluation code development, compact module tests for validation of the key functions of the components, technology integration assessment for fusion nuclear tests, etc., should be further developed toward DEMO in near-term. | |||||
| 書誌情報 |
Journal of Nuclear Materials 巻 511, p. 582-590, 発行日 2018-05 |
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| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1016/j.jnucmat.2018.05.045 | |||||
