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Kubo, Shigenobu; Chikazawa, Yoshitaka; Ohshima, Hiroyuki; Uchita, Masato*; Miyagawa, Takayuki*; Eto, Masao*; Suzuno, Tetsuji*; Matoba, Ichiyo*; Endo, Junji*; Watanabe, Osamu*; et al.
Mechanical Engineering Journal (Internet), 7(3), p.19-00489_1 - 19-00489_16, 2020/06
The authors are developing the design concept of pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDGs) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident.
Kubo, Shigenobu; Chikazawa, Yoshitaka; Ohshima, Hiroyuki; Uchita, Masato*; Miyagawa, Takayuki*; Eto, Masao*; Suzuno, Tetsuji*; Matoba, Ichiyo*; Endo, Junji*; Watanabe, Osamu*; et al.
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05
The authors are developing the design concept of pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDGs) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident.
Sato, Toshinori; Aoyagi, Kazuhei; Matsuzaki, Yoshiteru; Miyara, Nobukatsu; Miyakawa, Kazuya
Rock Dynamics; Experiments, Theories and Applications, p.575 - 580, 2018/06
Rock dynamics is one of key issue for research and development of techniques for safe geological disposal of high-level radioactive waste. Horonobe Underground Research Laboratory (URL) is off-site URL constructed in soft sedimentary rock to the depth of 350m with three shafts and three level experimental galleries. Earthquake-resistant design of underground openings, observation of seismic records and groundwater pressure change due to earthquakes, and excavation disturbed zone experiment have been performed relating to the study of rock dynamics in URL project. This paper shows current status of Horonobe URL project and results of earthquake-resistant design of shafts, observation of seismic records and groundwater pressure change due to the 2011 off the Pacific coast of Tohoku Earthquake.
Takeda, Nobukazu; Nakahira, Masataka
JAERI-Tech 2004-073, 59 Pages, 2005/01
JAERI-Tech-2004-073.pdf:11.36MB
The ITER toamak is composed of major components such as superconducting magnet and vacuum vessel whose operation temperatures are changed from room temperature to 4 K and room temperature to 200
C, respectively. The gravity support of the tokamak is flexible in order to accept the thermal deformation caused by temperature change. This structural feature causes the complex behaviors of the tokamak during seismic events. Therefore, the mechanical characteristics of the flexible support have to be investigated in detail. The present report describes the global plan of the series of vibration tests to estimate the seismic performance of the ITER tokamak. Although it is ideal that the vibration tests are carried out using a full-scale model, scale models are planned due to the limitation of the test facilities. The test results can be estimated by a scaling law. When the scaling law cannot be applied to some performances, the test is performed using a full-scale model. In addition, the other tests such as vacuum vessel and small-scaled models of the support structure are also planned.
Iigaki, Kazuhiko; Hanawa, Satoshi
Nuclear Engineering and Design, 233(1-3), p.59 - 70, 2004/12
Times Cited Count：3 Percentile：23.52(Nuclear Science & Technology)The high temperature engineering test reactor (HTTR) was constructed on a sand layer formed during the Quaternary era. A seismometry system was installed in the HTTR facility in order to performed seismic analyses using a seismic observation record. The analysis model in the design was improved so that the simulation analysis result reproduced the seismic observation record. The dynamic analysis was carried out using an improvement model in order to compare seismic forces in the design. As the result, it was confirmed that the seismic forces obtained by the improvement model was approximately more conservative than the seismic force used in the design.
Tada, Eisuke; Hada, Kazuhiko; Maruo, Takeshi; Safety Design/Evaluation Group
Purazuma, Kaku Yugo Gakkai-Shi, 78(11), p.1145 - 1156, 2002/11
no abstracts in English
Iyoku, Tatsuo; Inagaki, Yoshiyuki; Shiozawa, Shusaku; Futakawa, Masatoshi; *
Nuclear Technology, 99, p.169 - 176, 1992/08
Times Cited Count：8 Percentile：61.53(Nuclear Science & Technology)no abstracts in English
Iyoku, Tatsuo; Inagaki, Yoshiyuki; Shiozawa, Shusaku; *
Nuclear Technology, 99, p.158 - 168, 1992/08
Times Cited Count：2 Percentile：27.49(Nuclear Science & Technology)no abstracts in English
JAERI 1322, 157 Pages, 1991/04
no abstracts in English
Takeshita, Isao; Nomura, Masayuki; ; Izawa, Naoki; Yanagisawa, Hiroshi
Proc. of the 3rd Int. Conf. on Nuclear Fuel Reprocessing and Waste Management,Vol. 1, p.510 - 515, 1991/00
no abstracts in English
; *
Nihon Genshiryoku Gakkai-Shi, 27(2), p.145 - 158, 1985/00
Times Cited Count：2 Percentile：37.51(Nuclear Science & Technology)no abstracts in English
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Nihon Kikai Gakkai Rombunshu, C, 51(464), p.746 - 755, 1985/00
no abstracts in English
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JAERI 1282, 68 Pages, 1983/02
no abstracts in English
Bull.JSME, 208(16), p.1610 - 1617, 1982/00
no abstracts in English
; *; *
Nucl.Eng.Des., 71, p.195 - 215, 1982/00
Times Cited Count：8 Percentile：65.66(Nuclear Science & Technology)no abstracts in English
; *
JAERI-M 9265, 90 Pages, 1981/01
no abstracts in English
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Nihon Kikai Gakkai Rombunshu, C, 47(415), p.292 - 297, 1981/00
no abstracts in English
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JAERI-M 9199, 61 Pages, 1980/11
no abstracts in English
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Journal of Nuclear Science and Technology, 17(9), p.655 - 667, 1980/00
Times Cited Count：5 Percentile：53.45(Nuclear Science & Technology)no abstracts in English
; ; *; *; *
Nihon Genshiryoku Gakkai-Shi, 22(1), p.55 - 67, 1980/00
Times Cited Count：3 Percentile：41.98(Nuclear Science & Technology)no abstracts in English
