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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.
Oku, Tatsuo*; Ishihara, Masahiro
Nuclear Engineering and Design, 227(2), p.209 - 217, 2004/01
Times Cited Count：32 Percentile：87.09(Nuclear Science & Technology)The lifetime of graphite material and/or components has been discussed individually from different concepts, and sometimes gives confusion to material researchers as well as designers. The lifetime of graphite materials is determined based on the dimensional changes due to neutron irradiation, at which they return to their original dimensions after initially contracting. On the other hand, the lifetime of graphite components for HTGRs is defined based on a margin of the specified minimum ultimate strengths of the graphite to the stresses induced in the graphite components. As an example, the stresses induced in the graphite block for the HTTR were, then, compared with the limited stress value determined from the specified minimum ultimate strength, and the lifetime of the graphite component was evaluated and compared with that defined as dimensional changes. As a result, it was found that the lifetime of graphite components for HTGRs should be determined as the shorter one in the two lifetimes defined by the stress-strength relationship and by the dimensional changes.
Ishihara, Masahiro; Hanawa, Satoshi; Iyoku, Tatsuo; Shiozawa, Shusaku
Tanso, 2001(196), p.39 - 48, 2001/02
no abstracts in English
Eto, Motokuni; Ishiyama, Shintaro
Journal of Nuclear Science and Technology, 35(11), p.808 - 815, 1998/11
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Eto, Motokuni; Ishiyama, Shintaro; T.D.Burchell*; G.T.Yahr*
Journal of Nuclear Science and Technology, 34(5), p.476 - 483, 1997/05
Times Cited Count：5 Percentile：42.79(Nuclear Science & Technology)no abstracts in English
Ishihara, Masahiro; Aihara, Jun; Oku, Tatsuo*
Proc. of 14th Int. Conf. on Structural Mechanics in Reactor Technology, 2, p.455 - 462, 1997/00
no abstracts in English
Ishihara, Masahiro; Iyoku, Tatsuo; *
JCOSSAR95 Rombunshu, 0, p.199 - 206, 1995/00
no abstracts in English
Ishihara, Masahiro; Iyoku, Tatsuo; Futakawa, Masatoshi
Nucl. Eng. Des., 154, p.83 - 95, 1995/00
Times Cited Count：6 Percentile：54.86(Nuclear Science & Technology)no abstracts in English
Ishihara, Masahiro; Iyoku, Tatsuo; Shiozawa, Shusaku; *
JAERI-Tech 94-035, 61 Pages, 1994/12
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
Toyota, Junji; Iyoku, Tatsuo; Ishihara, Masahiro; Takikawa, Noboru; Shiozawa, Shusaku
JAERI-M 91-102, 61 Pages, 1991/07
no abstracts in English
Iyoku, Tatsuo; Ishihara, Masahiro; *; Shiozawa, Shusaku
JAERI-M 91-083, 31 Pages, 1991/05
no abstracts in English
Iyoku, Tatsuo; Ishihara, Masahiro; *; Shiozawa, Shusaku
JAERI-M 91-070, 32 Pages, 1991/05
no abstracts in English
Seki, Masahiro; Akiba, Masato; Araki, Masanori; ; Dairaku, Masayuki; *; Fukaya, Kiyoshi; Ogawa, Masuro; Ise, Hideo*
Fusion Engineering and Design, 15, p.59 - 74, 1991/00
Times Cited Count：17 Percentile：84.03(Nuclear Science & Technology)no abstracts in English
Eto, Motokuni; Fukaya, Kiyoshi; Ando, Toshiro; Takatsu, Hideyuki; Seki, Masahiro
Twentieth Biennial Conf. on Carbon, p.640 - 641, 1991/00
no abstracts in English
Eto, Motokuni; Fukaya, Kiyoshi; Oku, Tatsuo*; *; ; Takatsu, Hideyuki; Ando, Toshiro; Yamamoto, Masahiro; ; Shimizu, Masatsugu
Int. Symp. on Carbon New Processing and New Applications; Extended Abstracts,Vol. l, p.206 - 209, 1990/11
no abstracts in English
; ; ; ; Nekoya, Shinichi; ; *;
Nihon Genshiryoku Gakkai-Shi, 30(4), p.333 - 342, 1988/04
Times Cited Count：1 Percentile：29.57(Nuclear Science & Technology)no abstracts in English
