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Tanaka, Yoshihiro*; Kametaka, Masao*; Okazaki, Kazuhiko*; Suzuki, Kazushige*; Seshimo, Kazuyoshi; Aoki, Kazuhiro; Shimada, Koji; Watanabe, Takahiro; Nakayama, Kazuhiko
Oyo Chishitsu, 59(1), p.13 - 27, 2018/04
This paper aims to develop a methodology for understanding the fault activity by observing exposed fault planes without covering younger strata. Based on purpose, faults developed in relatively homogeneous rocks such granitic types are investigated as follows; Gosuke Dam upstream outcrop of Gosukebashi Fault and Funasaka-nishi outcrop of Rokkou Fault were selected for the study of an active fault; and K-3 outcrop of Rokkou Houraikyo Fault was chosen for a non-active fault.
Oguri, Hidetomo; Hasegawa, Kazuo; Ito, Takashi; Chishiro, Etsuji; Hirano, Koichiro; Morishita, Takatoshi; Shinozaki, Shinichi; Ao, Hiroyuki; Okoshi, Kiyonori; Kondo, Yasuhiro; et al.
Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.389 - 393, 2014/10
no abstracts in English
Suzuki, Kazuhiko; Jitsukawa, Shiro; Okubo, Nariaki; Takada, Fumiki
Nuclear Engineering and Design, 240(6), p.1290 - 1305, 2010/06
Times Cited Count：13 Percentile：65.22(Nuclear Science & Technology)Sugawara, Takanori; Suzuki, Kazuhiko; Nishihara, Kenji; Sasa, Toshinobu; Kurata, Yuji; Kikuchi, Kenji; Oigawa, Hiroyuki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 11 Pages, 2010/00
The investigations of the beam window which is one of the most critical components for the Accelerator Driven System (ADS) were performed. In the previous study, it was found that the buckling failure was the most severe failure mode for the beam window. Hence, the shape and the thickness of the beam window were optimized to prevent the buckling failure. The buckling analyses with initial imperfections were also performed to identify the level of the factor of safety (FS). The results showed that FS of 3 was conservative enough to ensure the integrity of the beam window. It was also shown that the ellipse shape concepts with the thickness of 2.0-2.4[mm] at the top and the thickness of 2.0-4.0[mm] at the transient part were acceptable under the current ADS design parameters.
Jitsukawa, Shiro; Suzuki, Kazuhiko; Okubo, Nariaki; Ando, Masami; Shiba, Kiyoyuki
Nuclear Fusion, 49(11), p.115006_1 - 115006_8, 2009/11
Times Cited Count：13 Percentile：45.06(Physics, Fluids & Plasmas)Irradiation often causes hardening and reduction of elongation as well as toughness degradation to a considerable degree. Data, however, indicate that these changes remain in manageable ranges for ITER-TBM application. Moreover, the saturation tendency of the changes with neutron dose suggests that some of the reduced activation martensitic steels are feasible even for future DEMO applications. It is also stressed that the development of a design methodology that is compatible with the large irradiation induced changes is essential to enable these applications. Modeling activities for the macroscopic mechanical response are expected to play key roles in design methodology development. Macroscopic models of plasticity (a constitutive equation) and cyclic softening behavior after irradiation are discussed. Significance of models to estimate microstructural changes during irradiation and beneficial effects of the heat treatment for irradiation performance are also introduced.
Uesaka, Mitsuru*; Onizawa, Kunio; Kasahara, Naoto*; Suzuki, Kazuhiko
Genshiryoku Kyokasho "Genshiro Kozo Kogaku", 374 Pages, 2009/04
no abstracts in English
Sugawara, Takanori; Suzuki, Kazuhiko; Nishihara, Kenji; Sasa, Toshinobu; Kurata, Yuji; Kikuchi, Kenji; Oigawa, Hiroyuki
JAEA-Research 2008-026, 91 Pages, 2008/03
JAEA-Research-2008-026.pdf:37.01MB
The design acceptance of the beam window which is one of the most critical components for the Accelerator Driven System (ADS) was investigated. From the simplified overall assessment for nuclear power plant, it was clarified that the buckling failure was the most severe failure mode for the beam window. The parametric survey for the thickness of the ellipse model was carried out to prevent the buckling failure by using the Finite Element Method code, FINAS. The buckling analyses with initial imperfections were also performed to discuss the factor of safety (FS). The results showed that FS of 3 was enough conservative to ensure the integrity of the beam window. It was also shown that the ellipse shape concepts with the thickness of 2.0
2.4 [mm] at the top and the thickness of 2.04.0 [mm] at the transient part were acceptable under the current ADS design parameters.
Suzuki, Kazuhiko
JAEA-Research 2007-062, 95 Pages, 2007/09
JAEA-Research-2007-062.pdf:9.8MB
Concepts of assuring structural integrity of plant components have been developed under limited conditions of either highly ductile or brittle materials. There are some cases where operation in severe conditions causes a significant reduction in ductility for materials with a high ductility before service. Current concepts of structural integrity assurance under the limited conditions of material properties or on the requirement of no significant changes in material properties even after long service will fail to incorporate expected technological innovations. A systematic concept of assuring the structural integrity should be developed for applying to ductile materials through brittle materials. In this report, first, background of concepts of existing structural codes are discussed. Next, issues of existing codes for brittle material parts are identified and then resolutions to the issues are proposed. Based on these discussions and proposals, a systematic concept is proposed.
Aoki, Shoji*; Wada, Masahiko*; Yamaji, Tetsuo*; Mori, Kensuke; Enoeda, Mikio; Hirose, Takanori; Suzuki, Kazuhiko
Do To Dogokin, 45(1), p.125 - 130, 2006/08
Chromium-zirconium copper (Cu-Cr-Zr) as precipitation hardened copper alloy is examined as one of the structural materials used for the ITER in vacuum vessel components (blanket and divertor etc.). The precipitation hardening in Cu-Cr-Zr is made by the solution treatment with rapid cooling to obtain the supersaturated solid solution of chromium and zirconium in copper, and the subsequent aging treatment to grow the refined precipitate consists of chromium and zirconium respectively. While the parts have been assembled and used by copper alloys already precipitation hardened in general use, the blanket parts will be done by the innovative method with the thermomechanical treatment set of the precipitation hardening at the same time as dissimilar material junction in the ITER blanket. In this research, the mechanical and electrical conductivity properties change was investigated under the wide range of thermomechanical treartment conditions in order to comprehend the conditions necessary to fulfill the excellent characteristics in Cu-Cr-Zr. Therefore, the influence of the quenching cooling rate condition after solution treatment and the other conditions on Cu-Cr-Zr was inspected by measuring electrical conductivity as the indication of the solution treatment state i.e. the supersaturated solid solution or the precipitation state and measuring the tensile test properties of the specimens that are prepared by the set of the solution treatments with some quenching cooling rate conditions and following aging treatments.
Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; et al.
JAERI-Research 2004-008, 383 Pages, 2004/06
JAERI-Research-2004-008.pdf:21.49MB
The present report contains the achievement of "Research and Development on Reduced-Moderation Light Water Reactor with Passive Safety Features", which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies.
Hirai, Takashi; Tanai, Kenji; Kikuchi, Hirohito*; Suzuki, Hideaki*; *; Onuma, Satoshi*
JNC TN8400 2003-009, 56 Pages, 2003/03
JNC-TN8400-2003-009.pdf:7.22MB
The objective of this report is to clarify mechanical effect of engineered barrier system to the unavoidable fault movement. From the basic policy of the second progess report by JNC, natural phenomenon which affect strongly to the geological disposal system shoult be avoided. However, small faults as sliprate "C" far from principal fault zone, are difficult to be found out completely. Therefore, it is important to evaluate the influence of these fault movements and to clarify stability and safety of the engineered barrier system. Accordingly, the effect of a rock displacement across a deposition holl was considered and the midium scale test was carried out. Then midium scale test was simulated by Finit Element Method in which the constitutive model of Tresca was adopted to analyze elastoplastic behavior of buffer material. From the result of the midium scale test and the analysis, it was realized that the buffer material diminish shear stress acting on the overpack. Further analytical study was conducted to evaluate the real scale engineered barrier system designed in the second progress report by JNC. From the study, it was apeared that stress in buffer corresponded to the stress calculated for the midium scale test model. Consequently, it was obvious that rock displacement, 80% of buffer thickness, didn't affect overpack if velocity of fault movement was under 10 cm/sec.
Kitamura, Toshikatsu; Togawa, Orihiko; Aramaki, Takafumi; Suzuki, Takashi; Mizutani, Yoshihiko*; Kabuto, Shoji*; Sudo, Kazuhiko*
JNC TN7200 2001-001, p.31 - 34, 2002/01
no abstracts in English
Gottdang, A.*; Klein, M.*; Mous, D. J. W.*; Kitamura, Toshikatsu; Mizutani, Yoshihiko*; Suzuki, Takashi; Aramaki, Takafumi; Togawa, Orihiko; Kabuto, Shoji*; Sudo, Kazuhiko*
AIP Conference Proceedings 576, p.403 - 406, 2001/00
no abstracts in English
Takachi, Kazuhiko; Suzuki, Hideaki*
JNC TN8400 99-041, 76 Pages, 1999/11
The buffer material is expected to maintain its low water permeability, self-sealing properties, radionuclides adsorption and retardation properties, thermal conductivity, chemical buffering properties, overpack supporting properties, stress buffering properties, etc. over a long period of time. Natural clay is mentioned as a material that can relatively satisfy above. Among the kinds of natural clay, bentonite when compacted is superior because (1)it has exceptionally low water permeability and properties to control the movement of water in buffer, (2)it fills void spaces in the buffer and fractures in the host rock as it swells upon water uptake, (3)it has the ability to exchange cations and to adsorb cationic radioelements. In order to confirm these functions for the purpose of safety assessment, it is necessary to evaluate buffer properties through laboratory tests and engineering-scale tests, and to make assessments based on the ranges in the data obtained. This report describes the procedures, test conditions, results and examinations on the buffer material of unconfined compression tests, one-dimensional consolidation tests, consolidated-undrained triaxial compression tests and consolidated-undrained triaxial creep tests that aim at getting hold of static mechanical properties. We can get hold of the relationship between the dry density and tensile stress etc. by Brazillian tests, between the dry density and unconfined compressive strength etc. by unconfined compression tests, between the consolidation stress and void ratio etc. by one-dimensional consolidation tests, the stress pass of each effective confining pressure etc. by consolidated-undrained triaxial compression tests and the axial strain rate with time of each axial stress etc. by consolidated-undrained triaxial creep tests.
; Hino, Ryutaro; Inagaki, Yoshiyuki; Takase, Kazuyuki; Ioka, Ikuo; Takada, Shoji; Suzuki, Kunihiro; Kunitomi, Kazuhiko; Maruyama, So;
JAERI 1333, 196 Pages, 1995/03
no abstracts in English
Ioka, Ikuo; Inagaki, Yoshiyuki; Suzuki, Kunihiro; Kunitomi, Kazuhiko;
Nihon Genshiryoku Gakkai-Shi, 37(3), p.217 - 227, 1995/00
Times Cited Count：1 Percentile：17.53(Nuclear Science & Technology)no abstracts in English
Ioka, Ikuo; Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Suzuki, Kunihiro
Nuclear Technology, 105, p.293 - 299, 1994/02
Times Cited Count：2 Percentile：37.25(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Ioka, Ikuo*; *
Nuclear Technology, 99, p.90 - 103, 1992/07
Times Cited Count：9 Percentile：65.13(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki; Suzuki, Kunihiro; Ioka, Ikuo*; Kunitomi, Kazuhiko;
Nihon Kikai Gakkai Rombunshu, B, 57(542), p.3520 - 3525, 1991/10
no abstracts in English
Ioka, Ikuo; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Shimomura, Hiroaki
Nihon Genshiryoku Gakkai-Shi, 32(12), p.1221 - 1223, 1990/12
Times Cited Count：0 Percentile：0.32(Nuclear Science & Technology)no abstracts in English
