TY - JOUR
T1 - Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond
AU - Nozawa, Takashi
AU - Ozawa, Kazumi
AU - Park, Chang Ho
AU - Park, Joon Soo
AU - Kohyama, Akira
AU - Hasegawa, Akira
AU - Nogami, Shuhei
AU - Hinoki, Tatsuya
AU - Kondo, Sosuke
AU - Yano, Toyohiko
AU - Shibayama, Tamaki
AU - Tsuchiya, Bun
AU - Shikama, Tatsuo
AU - Nagata, Shinji
AU - Tanaka, Teruya
AU - Iwakiri, Hirotomo
AU - Yamamoto, Yasushi
AU - Konishi, Satoshi
AU - Kasada, Ryuta
AU - Kondo, Masatoshi
AU - Kunugi, Tomoaki
AU - Yokomine, Takehiko
AU - Ueki, Yoshitaka
AU - Okubo, Nariaki
AU - Taguchi, Tomitsugu
AU - Tanigawa, Hiroyasu
N1 - Funding Information:
This paper has been prepared as an account of work assigned to the Japanese Implementing Agency under the Procurement Number IFERC-T1PA01-JA, IFERC-T1PA02-JA, IFERC-T1PA03-JA, IFERC-JA-13PA-T1T3T5 and IFERC-T1PA04-JA within the “Broader Approach Agreement” between the Government of Japan and the European Atomic Energy Community.
Publisher Copyright:
© 2018 Elsevier B.V.
PY - 2018/12/1
Y1 - 2018/12/1
N2 - 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.
AB - 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.
KW - Broader approach activities
KW - Chemical properties
KW - Fusion reactor materials
KW - Irradiation effects
KW - Mechanical properties
KW - Physical properties
KW - SiC/SiC composites
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U2 - 10.1016/j.jnucmat.2018.05.045
DO - 10.1016/j.jnucmat.2018.05.045
M3 - Article
AN - SCOPUS:85047276293
SN - 0022-3115
VL - 511
SP - 582
EP - 590
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -