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Osaki, Hirotaka; Shimazaki, Yosuke; Sumita, Junya; Shibata, Taiju; Konishi, Takashi; Ishihara, Masahiro
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 8 Pages, 2015/05
For the design on the VHTR graphite components, it is desirable to employ graphite material with higher strength. IG-430 graphite has been developed as an advanced candidate for VHTR. However, the new developed IG-430 does not have enough databases for the design of HTGR. In this paper, the compressive strength (Cs) of IG-430, one of important strengths for design data, is statistically evaluated. The component reliability is evaluated based on the safety factors defined by the graphite design code, and the applicability as the VHTR graphite material is discussed. It was found that IG-430 has higher strength (about 11%) and lower standard deviation (about 27%) than IG-110 which is one of traditional graphites used for HTGR, because the crack in IG-430 would not easy to propagate rather than IG-110. Since fracture probability for IG-430 is low, the higher reliability of core-component will be achieved using IG-430. It is expected that IG-430 is applicable for VHTR graphite material.
Ishihara, Masahiro; Sumita, Junya; Shibata, Taiju; Iyoku, Tatsuo; Oku, Tatsuo*
Nuclear Engineering and Design, 233(1-3), p.251 - 260, 2004/10
Times Cited Count：35 Percentile：88.7(Nuclear Science & Technology)The High Temperature Engineering Test Reactor (HTTR) constructed by Japan Atomic Energy Research Institute (JAERI) is a graphite-moderated and helium-gas-cooled reactor with prismatic fuel elements of hexagonal blocks. The reactor internal structures of the HTTR are mainly made up of graphite components. As well known, the graphite is a brittle material and there were no available design criteria for brittle materials. Therefore, JAERI had to develop the design criteria taking account of the brittle fracture behavior. In this paper, concept and key specification of the developed graphite design criteria is described, and also an outline of the quality control specified in the design criteria is mentioned.
Ishihara, Masahiro; Hanawa, Satoshi; Iyoku, Tatsuo; Shiozawa, Shusaku
Tanso, 2001(196), p.39 - 48, 2001/02
no abstracts in English
Akiba, Masato; Araki, Masanori; ; Ise, Hideo*; Nakamura, Kazuyuki; ; Dairaku, Masayuki; Tanaka, Shigeru
Journal of Nuclear Materials, 191-194, p.373 - 376, 1992/00
no abstracts in English
Ishihara, Masahiro; Iyoku, Tatsuo; *; ; Shiozawa, Shusaku
JAERI-M 91-154, 39 Pages, 1991/10
no abstracts in English
Ishihara, Masahiro; Iyoku, Tatsuo; *; ; Shiozawa, Shusaku
JAERI-M 91-153, 51 Pages, 1991/10
no abstracts in English
