Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond

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 struct...

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Bibliographic Details
Published in:Journal of nuclear materials 2018-12, Vol.511, p.582-590
Main Authors: 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
Format: Article
Language:English
Subjects:
Anisotropy
Breeding
Broader approach activities
Chemical properties
Composite materials
Corrosion
Corrosion products
Creep (materials)
Dependence
Durability
Electrical conductivity
Electrical resistivity
Fatigue
Fusion
Fusion reactor materials
High temperature
Irradiation
Irradiation effects
Mathematical models
Mechanical properties
Nuclear fusion
Organic chemistry
Physical properties
Potassium channels
R&D
Radiation
Radiation dosage
Radiation effects
Research & development
Residual stress
SiC/SiC composites
Silicon carbide
Technology assessment
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Summary: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.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2018.05.045