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Komabuchi, Mai*; Urushihara, Daisuke*; Asaka, Toru*; Fukuda, Koichiro*; Ohara, Takashi; Munakata, Koji*; Ishikawa, Yoshihisa*
Journal of the Physical Society of Japan, 89(3), p.034601_1 - 034601_5, 2020/03
Times Cited Count：2 Percentile：22.16(Physics, Multidisciplinary)Matsui, Hiroya; Tanno, Takeo; Hirano, Toru*; Goke, Mitsuo*; Kumasaka, Hiroo*; Tada, Hiroyuki*; Ishii, Takashi*
JAEA-Research 2010-043, 87 Pages, 2010/12
JAEA-Research-2010-043.pdf:3.99MB
The results are as follows (1) For the ventilation shaft at GL-350m, the crack tensor deformation analysis based on FY2004 work's results showed the calculated displacement was smaller than the measured displacement. A geometrical parameters of fractures in FY2004 work's result was different from one based on geological observation in the shaft. Therefore, the crack tensor of FY2004 work's results seems to be underestimated. (2) Large discontinuities with NE strike and high dipping observed in a shaft were major reason for the difference of crack tensors determined by borehole investigation from surface and geological observations in a shaft. Therefore, the crack tensor for pilot borehole investigation in a shaft was calculated as well and compared with each results. It was found that the fabric tensor is similar with it of geological observation and the vale was medium. (3) The crack tensor around GL-500m was estimated by relation of statistical quantities for fractures between GL-300m and GL-500m. Consequently, the deformation analysis based on the estimated crack tensor showed an increase in convergence and stress in the support system compared to FY2004 work's results.
Nagane, Satoru; Kitahara, Katsumi; Yoshikawa, Seiji; Miyasaka, Yasuhiko*; Fukumura, Nobuo*; Nishizawa, Ichio*
Dekomisshoningu Giho, (42), p.2 - 10, 2010/09
A reactor installed at the center part of the nuclear ship "Mutsu" has been stored safely and exhibited in a reactor room building since 1996. The reactor vessel and its internals are key components because of main radioactive wastes for the reasonable decommissioning plan in the future. This report describes the one-piece removal method as the one package of the reactor vessel with its internals intact with a shipping container or additional shields. The reactor vessel package (Max. 100 ton) will be classified acceptable for burial at the low level radioactive waste (LLW), which will be buried at a LLW pit facility under waste disposal regulations. And also, the package will be classified as an IP-2-equivalent package according to the requirement for Shipments and Packagings.
Kitagaki, Toru; Tasaka, Masayuki; Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Washiya, Tadahiro; Kobayashi, Tsuguyuki*
Proceedings of 17th International Conference on Nuclear Engineering (ICONE-17) (CD-ROM), 5 Pages, 2009/06
JAEA has been developing a reliable disassembly system for FBR fuel reprocessing as a part of Fast Reactor Cycle Technology Development (FaCT). We fabricated the disassembly system testing machine. In this paper, we described design of it.
Kikuchi, Yasuyuki; ; Tasaka, Kanji; ; *; Katsuragi, Satoru
JAERI-M 6001, 80 Pages, 1975/02
no abstracts in English
Kikuchi, Yasuyuki; Tasaka, Kanji; ; ; Katsuragi, Satoru
JAERI-M 5492, 71 Pages, 1973/12
no abstracts in English
Kambara, Toyozo; Uno, Hidero; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Takayanagi, Hiroshi; Fujimura, Tsutomu; Morita, Morito; Ichihara, Masahiro; et al.
JAERI 1045, 11 Pages, 1963/03
no abstracts in English
JRR-2 Control Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.
JAERI 1027, 57 Pages, 1962/09
no abstracts in English
Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Haginoya, Kinichi; Kohayakawa, Toru; Yamaki, Jikei; Yokota, Mitsuo; Horiki, Oichiro; Yuhara, Shunichi; et al.
JAERI 1023, 120 Pages, 1962/09
no abstracts in English
JRR-2 Operations Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Haginoya, Kinichi; Kohayakawa, Toru; Yamaki, Jikei; Yokota, Mitsuo; Horiki, Oichiro; et al.
JAERI 1024, 79 Pages, 1962/08
no abstracts in English
JRR-2 Critical Experiments Group; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.
JAERI 1025, 62 Pages, 1962/03
no abstracts in English
Kitagaki, Toru; Washiya, Tadahiro; Tasaka, Masayuki
no journal, ,
no abstracts in English
Kitagaki, Toru; Tasaka, Masayuki; Washiya, Tadahiro; Kobayashi, Tsuguyuki
no journal, ,
JAEA has been developing a reliable disassembly system for FBR fuel reprocessing as a part of Fast Reactor Cycle Technology Development (FaCT). We fabricated a testing machine of disassembly system. In this poster, we described design of this device.
Sueoka, Michiharu; Akasaka, Hiromi; Sugimura, Toru; Kawamata, Yoichi; Kurihara, Kenichi; Naito, Osamu
no journal, ,
no abstracts in English
Kawamata, Yoichi; Naito, Osamu; Kurihara, Kenichi; Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Sugimura, Toru
no journal, ,
no abstracts in English
Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Kitagaki, Toru; Washiya, Tadahiro; Kobayashi, Tsuguyuki*; Tasaka, Masayuki*
no journal, ,
no abstracts in English
Kitagaki, Toru; Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Tasaka, Masayuki*; Washiya, Tadahiro; Kobayashi, Tsuguyuki*
no journal, ,
no abstracts in English
Shimada, Takashi*; Kitagaki, Toru; Tasaka, Masayuki*; Washiya, Tadahiro; Tsubota, Shuho*; Kohata, Yukifumi*; Nishikawa, Hideaki*; Kuroda, Kazuhiko*
no journal, ,
no abstracts in English
Kuroda, Kazuhiko*; Kitagaki, Toru; Higuchi, Hidetoshi; Tasaka, Masayuki*; Washiya, Tadahiro; Toya, Yuichi*; Nishikawa, Hideaki*; Karatsu, Fumiaki*
no journal, ,
no abstracts in English
Washiya, Tadahiro; Kitagaki, Toru; Higuchi, Hidetoshi; Koizumi, Kenji; Kobayashi, Tsuguyuki*; Koyama, Tomozo; Tasaka, Masayuki*
no journal, ,
JAEA have been developing a reliable fuel disassembly and shearing systems in cooperation with Japan Atomic Power Company (JAPC). We proposed a disassembly system utilizing mechanical cutting and pulling method. We designed and fabricated an engineering-scale test device, and confirming the system performance by using the simulated fuel assembly. And we proposed new shearing procedure as short-stroke cutting to provide highly fragmented fuel to realize efficient fuel dissolution required from the uranium crystallization process. We designed and fabricated the fuel transfer device and carried out some experiment to confirm that the fuel fragmentation rate and shared stroke was chosen to be 1 cm. In this paper, we will report the latest experiment for these systems.
