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Kato, Atsushi; Yamamoto, Tomohiko; Ando, Masato; Chikazawa, Yoshitaka; Murakami, Hisatomo*; Oyama, Kazuhiro*; Kaneko, Fumiaki*; Higurashi, Koichi*; Chanteclair, F.*; Chenaud, M.-S.*; et al.
EPJ Nuclear Sciences & Technologies (Internet), 8, p.11_1 - 11_10, 2022/06
This paper provides an overview of plant system studies to establish a common technical view for Sodium-cooled Fast Reactor concept between France and Japan based on ASTRID600 and the new concept with downsized output called ASTRID150. One of important issues on a reactor structure design is to enhance seismic resistance to be tolerable against strong earthquake such that postulated in Japan. A concept of High Frequency Design is shared, and the design options related to HFD have been examined and design recommendations are established. In addition, this paper include results of studies for a steam generator, a decay heat removal system, a fuel handling system and a containment vessel.
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.
Saito, Hiroyuki*; Higurashi, Koichi*; Kanazawa, Mitsuhiro*; Oki, Shigeo
no journal, ,
no abstracts in English
Higurashi, Koichi*; Akiyama, Yo*; Yamano, Hidemasa
no journal, ,
Of important items which would be relected to safety design guideline (SDG), overview of item 14 "formation and load of containment boundary" related to containment system is described based on design concept of next generation SFR in Japan.
Fukuchi, Ikuo*; Higurashi, Koichi*; Shiraki, Takako*; Sugino, Kazuteru; Oki, Shigeo
no journal, ,
no abstracts in English
Saito, Hiroyuki*; Higurashi, Koichi*; Masuyama, Daisuke*; Oki, Shigeo; Ohgama, Kazuya; Maeda, Seiichiro
no journal, ,
no abstracts in English
Kubo, Shigenobu; Higurashi, Koichi*; Miyagawa, Takayuki*
no journal, ,
Safety design concept for a pool-type sodium cooled fast reactor was investigated based on the safety design criteria and safety design guidelines developed in the generation IV reactor international forum.
Kubo, Shigenobu; Higurashi, Koichi*; Shibata, Akihiro*
no journal, ,
This paper describes progress of pool-type next generation sodium-cooled fast reactor (SFR) design study in Japan. Safety design criteria and safety design guidelines for SFR developed in the frame of generation IV international forum are fully applied in the safety design. In order to eliminate complete loss of heat removal, decay heat removal facilities are enhanced and their performance is evaluated.