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Matsunaga, Shoko*; Matsubara, Shinichiro*; Kato, Atsushi; Yamano, Hidemasa; D
derlein, C.*; Guillemin, E.*; Hirn, J.*
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05
This paper presents a design of Curie Point Electro-Magnet (CPEM) which will be installed as a passive shutdown system for a French Sodium-cooled Fast Reactor (ASTRID) development program which is conducted in collaboration between France and Japan. To confirm CPEM design validity, a qualification program for CPEM is developed on the basis of past comprehensive test series of Self-Actuated Shutdown System (SASS) in Japan. The main outcome of this paper is results of holding force tests in hot gas, which satisfy design requirements. Moreover, the result of a numerical magnetic field analysis showed the same tendency as that of the holding force test.
Saito, Hiroyuki*; Yamada, Yumi*; Oyama, Kazuhiro*; Matsunaga, Shoko*; Yamano, Hidemasa; Kubo, Shigenobu
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04
A self-actuated shutdown system (SASS) is a passive device, which can detach a control rod for reactor shutdown in response to excessive increase in coolant temperature. Since a detachment temperature, which triggers release of a control rod, and a response time are identified as important parameters for validity analyses, this study focused on investigation of the response time and the detachment temperature, and safety analysis to see feasibility of the SASS in low power. For this purpose, design modifications were made to shorten the response time and three-dimensional thermal-hydraulic analysis in a low power operation was carried out in order to confirm the response time. The resulting detachment temperature level is lower than previous studies, leading to improved safety parameters. Based on improved parameters, a safety analysis to see feasibility of the SASS in low power was carried out. From this safety evaluation, it was confirmed that core damage can be prevented by the SASS with flow collector in the case of LOF type ATWS event.
Chikazawa, Yoshitaka; Aizawa, Kosuke; Kato, Atsushi; Eto, Masao*; Matsunaga, Shoko*
no journal, ,
A next generation sodium cooled reactor introduce a flexible arm fuel handling machine to reduce reactor vessel diameter. In this study, prevention of jamming at the movable parts of the fuel handling machine and recovery from jamming is investigated.
Aizawa, Kosuke; Kawasaki, Nobuchika; Chikazawa, Yoshitaka; Eto, Masao*; Matsunaga, Shoko*
no journal, ,
When the rotating plug rotates in the presence of uplifted core fuel subassembly, the core fuel subassembly hits the upper internal structure. Therefore, the horizontal type under sodium viewer will be adopted to the next generation sodium-cooled fast reactor in order to check the obstacle between the core top and the upper internal structure bottom before the movement of rotating plug. In this study, the conceptual design of horizontal type under sodium viewer for next generation sodium-cooled fast reactor was conducted.
Saito, Hiroyuki*; Yamada, Yumi*; Oyama, Kazuhiro*; Matsunaga, Shoko*; Kubo, Shigenobu; Yamano, Hidemasa
no journal, ,
The effectiveness of self-actuated shutdown structure (SASS) for representative LOF-type ATWS event in a low-power operation was confirmed after the definition of a response time by three-dimensional thermal hydraulics analysis for its modified structure in order to improve the response characteristics of SASS.
Aizawa, Kosuke; Yamano, Hidemasa; Matsunaga, Shoko*; Nakamura, Hironori*; Shimada, Ren*; Uchita, Masato*
no journal, ,
no abstracts in English
Shimada, Ren*; Matsunaga, Shoko*; Kajitani, Fumito*; Yoshida, Yoshihiko*; Inuzuka, Taisuke*; Yoshida, Keisuke*; Futagami, Satoshi; Kameyama, Masatoshi*
no journal, ,
no abstracts in English