@article{oai:repo.qst.go.jp:00049297,
 author = {Nozawa, Takashi and Ozawa, Kazumi and Park, ChangHo and Park, Joon-Soo and Kohyama, Akira and Hasegawa, Akira and Nogami, Shuhei and Hinoki, Tatsuya and Kondo, Sosuke and Yano, Toyohiko and Shibayama, Tamaki and Tsuchiya, Bun and Shikama, Tatsuo and Nagata, Shinji and Tanaka, Teruya and Iwakiri, Hirotomo and Yamamoto, Yasushi and Konishi, Satoshi and Kasada, Ryuta and Kondo, Masatoshi and Kunugi, Tomoaki and Yokomine, Takehiko and Ueki, Yoshitaka and Okubo, Nariaki and Taguchi, Tomitsugu and Tanigawa, Hiroyasu and 野澤 貴史 and 小沢 和巳 and 朴 昶虎 and 田口 富嗣 and 谷川 博康},
 journal = {Journal of Nuclear Materials},
 month = {May},
 note = {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.},
 pages = {582--590},
 title = {Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond},
 volume = {511},
 year = {2018}
}