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Sumita, Junya; Shibata, Taiju; Fujita, Ichiro*; Kunimoto, Eiji*; Yamaji, Masatoshi*; Eto, Motokuni*; Konishi, Takashi*; Sawa, Kazuhiro
Nuclear Engineering and Design, 271, p.314 - 317, 2014/05
Times Cited Count：11 Percentile：64.59(Nuclear Science & Technology)In this study, in order to develop evaluation method for material properties and to evaluate the irradiation-induced property changes under higher neutron doses for IG-430, the oxidation and densification effects on elastic modulus of IG-430 were investigated. Moreover, the correlation of the microstructure based on the X-ray tomography images and the material properties was discussed. It was shown that the elastic modulus of the densified graphite depends on only the closed pores and it is possible to evaluate the material properties of graphite by using X-ray tomography method. However, it is necessary to take into account of the change in the number and shape of closed pores in the grain to simulate the elastic modulus of the highly oxidized and irradiated materials by the homogenization analysis.
Fujita, Ichiro*; Eto, Motokuni*; Osaki, Hirotaka; Shibata, Taiju; Sumita, Junya; Konishi, Takashi; Yamaji, Masatoshi; Kunimoto, Eiji
JAEA-Research 2013-004, 20 Pages, 2013/07
JAEA-Research-2013-004.pdf:2.4MB
Graphite components in HTGR and VHTR may be oxidized by impurities in coolant helium-gas even at normal operation, as well as by air at air-ingress accident. In this study, by air-oxidation test at 520-900
C, oxidation characteristics of IG-110 and IG-430 graphites, and associated decrease in compressive strength were examined. The following results were obtained. (1) The activation energy of the air-oxidation for IG-430 is 176 kJ/mol being almost same as for IG-110, though the oxidation rate for IG-430 is less than a half of that for IG-110. (2) There are correlations between density change and decrease in compressive strength. Decrease in strength is the largest in case that the oxidation temperature is lower than 600 C where the homogenous oxidation occurs. (3) In the process of oxidation, amorphous binder regions are predominantly oxidized. It suggests that peeling-off of cokes grains is necessary to be considered for oxidation weight loss, as well as gasification.
Sumita, Junya; Shibata, Taiju; Fujita, Ichiro*; Kunimoto, Eiji*; Yamaji, Masatoshi*; Eto, Motokuni*; Konishi, Takashi*; Sawa, Kazuhiro
Proceedings of 6th International Topical Meeting on High Temperature Reactor Technology (HTR 2012) (USB Flash Drive), 6 Pages, 2012/10
In this study, in order to develop evaluation method for material properties and to evaluate the irradiation-induced property changes under higher neutron doses for IG-430, the oxidation and densification effects on elastic modulus of IG-430 were investigated. Moreover, the correlation of the microstructure based on the X-ray tomography images and the material properties was discussed. It was shown that the elastic modulus of the densified graphite depends on only the closed pores and it is possible to evaluate the material properties of graphite by using X-ray tomography method. However, it is necessary to take into account of the change in the number and shape of closed pores in the grain to simulate the elastic modulus of the highly oxidized and irradiated materials by the homogenization analysis.
Eto, Motokuni*; Konishi, Takashi*; Shibata, Taiju; Sumita, Junya
IOP Conference Series; Materials Science and Engineering, 18(16), p.162003_1 - 162003_6, 2011/09
Times Cited Count：4 Percentile：87.38(Materials Science, Ceramics)High Temperature Gas-cooled Reactor (HTGR) and Very High Temperature Reactor (VHTR) are attractive nuclear reactors to obtain high temperature helium gas to the reactor outlet. To enhance the thermal efficiency, the core internals of HTGR/VHTR are subjected to the very severe high temperature condition. The carbon fiber reinforced carbon-carbon composite (C/C composite) is one of the advanced material candidates for the control rod sheath of the reactors because of its excellent thermal resistance and stability in the severe condition. The R&Ds on the C/C composite application to HTGR have been carried out since 1990'. JAEA and Toyo Tanso have been in collaboration with each other in the R&Ds. The development of control rod made of C/C composite is recently focused as one of the important subjects to develop the VHTR in the international R&Ds. The scheme of the development of JAEA is categorized as the following phases; (1) Database establishment, (2) Design and manufacturing of component and (3) Demonstration test by HTTR. At the initial stage of the development in 1990' in JAERI, the feasibility of the control rod using C/C composite was demonstrated by a conceptual design. The phase (2) is planned to be completed within 5 years. This paper presents the review of the development of the control rod made of C/C composite and the recent R&D results.
Shibata, Taiju; Kunimoto, Eiji*; Eto, Motokuni*; Shiozawa, Shusaku; Sawa, Kazuhiro; Oku, Tatsuo*; Maruyama, Tadashi*
Journal of Nuclear Science and Technology, 47(7), p.591 - 598, 2010/07
Times Cited Count：10 Percentile：56.32(Nuclear Science & Technology)no abstracts in English
Shibata, Taiju; Eto, Motokuni*; Kunimoto, Eiji*; Shiozawa, Shusaku; Sawa, Kazuhiro; Oku, Tatsuo*; Maruyama, Tadashi*
JAEA-Research 2009-042, 119 Pages, 2010/01
JAEA-Research-2009-042.pdf:26.28MB
For the design of the graphite components in the High Temperature Engineering Test Reactor (HTTR), the graphite structural design code for the HTTR etc. were applied. However, general standard systems for the High Temperature Gas-cooled Reactor (HTGR) have not been established yet. The authors had studied on the technical issues which is necessary for the establishment of a general standard system for the graphite components in the HTGR. The results of the study were documented and discussed at a "Special committee on research on preparation for codes for graphite components in HTGR" at Atomic Energy Society of Japan (AESJ). As a result, "Draft of Standard for Graphite Core Components in High Temperature Gas-cooled Reactor" was established. In this draft standard, the graphite components are classified three categories (A, B and C) in the standpoints of safety functions and possibility of replacement. For the components in the each class, design standard, material and product standards, and in-service inspection and maintenance standard are determined. This draft standard is the first standard in the world which shows the concept of standard for the graphite core components in HTGR.
Kunimoto, Eiji; Shibata, Taiju; Shimazaki, Yosuke; Eto, Motokuni*; Shiozawa, Shusaku; Sawa, Kazuhiro; Maruyama, Tadashi*; Oku, Tatsuo*
JAEA-Research 2009-008, 28 Pages, 2009/06
JAEA-Research-2009-008.pdf:4.6MB
The VHTR is being focused and developed internationally. In Japan, the HTTR of the JAEA is in operation, and research and development for the development of commercial HTGRs are carried out. Nuclear graphites are used for core components of the HTGRs and expansion of irradiation data is necessary when enough irradiation data are not established, because the graphite components in the HTGRs are used at severer condition than that in the HTTR. The necessary database can be established by expansion of existing irradiation data with appropriate interpolation and extrapolation methods. This paper shows the reasonable interpolation and extrapolation method for IG-110 graphite which is used for the HTTR and a major candidate for the VHTR. The interpolation and extrapolation method was developed so as to be general by using the irradiation data of the other graphites. As a result, irradiation properties of the IG-110 graphite were successfully expanded to the VHTR condition for the first time and the irradiation properties being necessary for the design could be developed.
Eto, Motokuni; Ishii, Toshimitsu; Inagaki, Terumi*; Okamoto, Yoshizo*
Carbon, 40(3), p.285 - 294, 2002/03
Times Cited Count：9 Percentile：36.89(Chemistry, Physical)no abstracts in English
Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*
Fusion Engineering and Design, 58-59, p.869 - 873, 2001/11
Times Cited Count：2 Percentile：19.66(Nuclear Science & Technology)no abstracts in English
Ishiyama, Shintaro; Eto, Motokuni
Nihon Genshiryoku Gakkai-Shi, 43(11), p.1159 - 1166, 2001/11
Times Cited Count：2 Percentile：19.66(Nuclear Science & Technology)no abstracts in English
Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Nakahira, Masataka
Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08
Fatigue test of the weldments was performed to investigate their fatigue behavior and the effect of the incomplete penetrations on the fatigue strength. Fatigue crack propagation test of their weld metals was also carried out using CT specimen. By calculating stress intensity factors of the weldments contained the incomplete penetrations and cracks using FEM analysis, the fatigue crack propagation rates of weldments were evaluated and compared those of their weld metals. Fatigue life of the weldments was evaluated based on fracture mechanics to discuss the effect of incomplete penetrations on the fatigue strength. As the results, the incomplete penetration behaved as a crack and most of total fatigue life for the weldment was crack propagation life. The crack propagation rates of weldment were in accordance with those of the weld metals. The fatigue strength of the weldment was considerably lower than that of smoothed specimen. The incomplete penetrations affected greatly the fatigue strength of the weldments even if the depth of incomplete penetrations was small.
Kogawa, Hiroyuki; Futakawa, Masatoshi; Ishikura, Shuichi*; Kikuchi, Kenji; Hino, Ryutaro; Eto, Motokuni
International Journal of Impact Engineering, 25(1), p.17 - 28, 2001/01
Times Cited Count：3 Percentile：23.9(Engineering, Mechanical)no abstracts in English
/SiC
compositeFutakawa, Masatoshi; Tanabe, Yuji*; Wakui, Takashi*; Kogawa, Hiroyuki; Hino, Ryutaro; Eto, Motokuni
International Journal of Impact Engineering, 25(1), p.29 - 40, 2001/01
Times Cited Count：11 Percentile：48.17(Engineering, Mechanical)no abstracts in English
Johnson, W. R.*; Trester, P. W.*; Sengoku, Seio; Ishiyama, Shintaro; Fukaya, Kiyoshi; Eto, Motokuni; Oda, Tomomasa*; Hirohata, Yuko*; Hino, Tomoaki*; Tsai, H.*
Journal of Nuclear Materials, 283-287(Part1), p.622 - 627, 2000/12
Times Cited Count：2 Percentile：19.44(Materials Science, Multidisciplinary)no abstracts in English
Ishii, Toshimitsu; Omi, Masao; Saito, Junichi; Hoshiya, Taiji; Ooka, Norikazu; Jitsukawa, Shiro; Eto, Motokuni
Journal of Nuclear Materials, 283-287(Part.2), p.1023 - 1027, 2000/12
Times Cited Count：12 Percentile：62.16(Materials Science, Multidisciplinary)no abstracts in English
Saito, Shigeru; Fukaya, Kiyoshi; Ishiyama, Shintaro; Eto, Motokuni; Sato, Ikuo*; Kusuhashi, Mikio*; Hatakeyama, Tsuyoshi*; Takahashi, Heishichiro*; Kikuchi, Mitsuru
Journal of Nuclear Materials, 283-287(Part1), p.593 - 596, 2000/12
Times Cited Count：1 Percentile：12.1(Materials Science, Multidisciplinary)no abstracts in English
Ishiyama, Shintaro; Akiba, Masato; Eto, Motokuni
Nihon Genshiryoku Gakkai-Shi, 42(12), p.1334 - 1342, 2000/12
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Ishiyama, Shintaro; Baba, Shinichi; Fukaya, Kiyoshi; Eto, Motokuni; Akiba, Masato; Sato, Makoto*; Araki, Toshimitsu*; Yamaguchi, Seiji*; Yamazaki, Seiichiro*
Nihon Genshiryoku Gakkai-Shi, 42(7), p.669 - 677, 2000/07
no abstracts in English
Futakawa, Masatoshi; Wakui, Takashi*; Ioka, Ikuo; Eto, Motokuni
Journal of the European Ceramic Society, 20(8), p.1135 - 1143, 2000/05
Times Cited Count：5 Percentile：44.86(Materials Science, Ceramics)no abstracts in English
Saito, Shigeru; Fukaya, Kiyoshi; Ishiyama, Shintaro; Eto, Motokuni; Akiba, Masato
JAERI-Research 2000-006, p.57 - 0, 2000/02
JAERI-Research-2000-006.pdf:20.86MB
no abstracts in English
