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Tanaka, Masaaki; Nakada, Kotaro*; Kudo, Yoshiro*
Nihon Kikai Gakkai-Shi, 123(1222), p.26 - 29, 2020/09
In the nuclear engineering, simulations are used in radiation, thermal hydraulic, chemical reaction, and structural fields, and the integrated fields thereof, to be applied to the design, construction and operation of nuclear facilities. This article describes brief history of discussion in the AESJ to the publication and introductory explanation of the procedures in the five major elements described in the "Guideline for Credibility Assessment of Nuclear Simulations (AESJ-SC-A008: 2015)". And also, a practical experience of the V&V activity according to the fundamental concept indicated in the Guideline is introduced.
Kawabata, Kuniaki; Osumi, Hisashi*; Onishi, Ken*
Nihon Kikai Gakkai-Shi, 122(1211), p.16 - 17, 2019/10
no abstracts in English
Koma, Yoshikazu; Niibori, Yuichi*
Nihon Kikai Gakkai-Shi, 122(1211), p.21 - 23, 2019/10
International Topical Workshop on Fukushima Decommissioning Research was held in March 2019 by the Japan Society of Mechanical Engineers and the Atomic Energy Society of Japan. Result of track for waste management technologies among 5 tracks is outlined.
Washiya, Tadahiro; Suzuki, Shunichi*
Nihon Kikai Gakkai-Shi, 122(1211), p.13 - 15, 2019/10
International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) was held in last May. In this report, the out-line of Track-2: Debris Removal Strategy, Risk, Debris Characterization was described. In this Task-2, "1F decommissioning strategy plan 2019" was introduced by NDF, and challenging tasks are explained. As 1F's R&D issues, debris cutting technologies, dust generation behavior analysis and risk evaluation was reported. In this paper, the out-line of Track 2 will be reported.
Wakaida, Ikuo; Hasegawa, Shuichi*; Tadokoro, Takahiro*
Nihon Kikai Gakkai-Shi, 122(1211), p.18 - 20, 2019/10
no abstracts in English
Kawamura, Hiroshi
Nihon Kikai Gakkai-Shi, 117(1151), p.688 - 689, 2014/10
no abstracts in English
Kobayashi, Yasuhiko
Nihon Kikai Gakkai-Shi, 115(1126), P. 669, 2012/09
no abstracts in English
Suzuki, Mitsuhiro
Nihon Kikai Gakkai-Shi, 109(1056), P. 40, 2006/11
A new method to estimate almost all coolant mass change during a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR) was developed as an important technique for accident management (AM) measures. An AM action to inject water into a PWR is required by a key parameter of core exit thermocouples (CETs) in many OECD countries but by a reactor vessel level meter in a few countries. It is obvious that the CETs can give no information on the primary coolant mass change but indication of core heat-up. The new method uses the primary loop (PL) level meters designed to measure water level in each steam generator (SG) outlet region, and the reactor vessel level indication system (RVLIS) in the Westinghouse-type PWR in addition to the pressurizer level meter. The author clarified through the ROSA/LSTF experiments that these three kinds of level meters are useful to estimate more than 80% of the total coolant mass change between the initial and core heat-up conditions. It is important to understand the role of PL level meters which almost cover an insensitive coolant mass detection range of the RVLIS before the core heat-up initiation.
Shibanuma, Kiyoshi
Nihon Kikai Gakkai-Shi, 109(1051), p.466 - 467, 2006/06
Fusion energy will be a strong candidate as a resource in the future energy. For realization of the fusion reactor, International Thermonuclear Experimental Reactor (ITER) will be constructed in France under the international collaboration of Japan, EU, US, RF, China, Korea and India. The in-vessel of the ITER is activated due to neutron because the fusion energy is produced by a nuclear reaction in the same manner of fission. In the maintenance of in-vessel components, a robot is therefore required instead of human due to high 
radiation in the reator. Based on the above background, JAEA is under development of a maintenance robot for ITER in-vessel components. In addition, a rescue robot has been developed as a basis in order to apply to the accidents such as critical accident in the JCO. In the present paper, the outline and features of two kinds of representative nuclear robots are described.
Igarashi, Takahiro; Ogata, Shuji*
Nihon Kikai Gakkai-Shi, 108(1043), p.812 - 814, 2005/10
no abstracts in English
Hino, Ryutaro; Yokomizo, Hideaki; Yamazaki, Yoshishige; Hasegawa, Kazuo; Suzuki, Hiromitsu; Soyama, Kazuhiko; Hayashi, Makoto*; Haga, Katsuhiro; Kaminaga, Masanori; Sudo, Yukio*; et al.
Nihon Kikai Gakkai-Shi, 107(1032), p.851 - 882, 2004/11
no abstracts in English
Aso, Tomokazu
Nihon Kikai Gakkai-Shi, 107(1029), P. 43, 2004/08
no abstracts in English
Oka, Kiyoshi
Nihon Kikai Gakkai-Shi, 106(1019), p.765 - 768, 2003/10
no abstracts in English
Haga, Katsuhiro
Nihon Kikai Gakkai-Shi, 104(993), P. 533, 2001/08
no abstracts in English
Kaminaga, Masanori
Nihon Kikai Gakkai-Shi, 103(981), p.42 - 43, 2000/08
no abstracts in English
Yanagihara, Satoshi
Nihon Kikai Gakkai-Shi, 100(948), p.1174 - 1178, 1997/11
no abstracts in English
Tanaka, Mitsugu
Nihon Kikai Gakkai-Shi, 100(938), 93 Pages, 1997/01
no abstracts in English
Tanaka, Toshiyuki
Nihon Kikai Gakkai-Shi, 99(937), 1039 Pages, 1996/12
no abstracts in English
