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Kato, Atsushi; Chikazawa, Yoshitaka; Nabeshima, Kunihiko; Iwasaki, Mikinori*; Akiyama, Yo*; Oya, Takeaki*
Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.593 - 600, 2015/05
Japan sodium cooled fast reactor is the advanced loop type reactor developing in Japan. After the Fukushima-Dai-ichi NPP accident, system enhancement against severe accident have been investigated mainly for residual decay heat removal system, spent fuel storage system and emergency power sources in order to satisfy the safety design criteria for Generation IV SFR. This paper describes principle of the building layout design and the actual approach to be consistent with the recent design enhancement in JSFR. From the perspective of greater ability to withstand severe events, the principles of the building layout design as the measures against aircraft attack and the consequential fire, and tsunami are introduced in order to avoid local event initiating and simultaneous redundant failure of the safety grade facilities and could achieve lowering risk of the loss of all stuck and maintaining the essential power supply.
Isono, Kenichi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Dozaki, Koji*; Oya, Takeaki*; Yui, Masahiro*
Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 7 Pages, 2014/07
Aiming at enabling maintenance and repair of almost all components in JSFR demonstration reactor to a level equivalent to that attained for the light water reactors, we identified a number of parts which have difficulty in maintenance and repair in main components of the reactor structure and the primary/secondary main coolant system. And we defined the criteria for design improvement and then provided candidates of improvement measures for the identified parts. Furthermore, we made a modification of the plant design in a consistent manner integrating the improvements investigated for each major component. A series of evaluations were conducted to check the feasibility as a power plant. As the result, we found that the concept could be adopted not only to the demonstration reactor (750 MWe) but to the commercial one (1500 MWe).
Yamamoto, Tomohiko; Kato, Atsushi; Chikazawa, Yoshitaka; Ito, Kei; Iwasaki, Mikinori*; Akiyama, Yo*; Oya, Takeaki*
Proceedings of 2013 International Congress on Advances in Nuclear Power Plants (ICAPP 2013) (USB Flash Drive), 9 Pages, 2013/04
The Japan sodium-cooled fast reactor (JSFR) is planning to adopt a steel-plate reinforced concrete (SC) structure reactor building and an advanced seismic isolation system for reactor building. In the response of Fukushima Dai-ichi Nuclear Power Plant (Fukushima I NPP) accident, the evaluation and countermeasure study of earthquake, and other external hazards on JSFR has been analyzed based on 2010 JSFR design. This paper describes the detail of evaluation and countermeasure of earthquake, tsunami and other external hazards to JSFR reactor building.
Yamamoto, Tomohiko; Kato, Atsushi; Chikazawa, Yoshitaka; Oya, Takeaki*; Iwasaki, Mikinori*; Hara, Hiroyuki*; Akiyama, Yo*
Proceedings of 2012 International Congress on Advances in Nuclear Power Plants (ICAPP '12) (CD-ROM), p.500 - 508, 2012/06
Japan Sodium-cooled Fast Reactor (JSFR) is planning to adopt the new concepts of reactor building. One is that the steel plate reinforced concrete is adopted for containment vessel and reactor building. The other is the advanced seismic isolation system. This paper describes the detail of new concepts for JSFR reactor building and engineering evaluation of the new concepts.
Yamamoto, Tomohiko; Kato, Atsushi; Chikazawa, Yoshitaka; Negishi, Kazuo; Oya, Takeaki*; Iwasaki, Mikinori*; Hara, Hiroyuki*; Akiyama, Yo*
no journal, ,
JSFR plans to adopt the steel-plate reinforced concrete (SC) structure for the containment vessel (CV). Since it has not been proven for CV as of last year, material test and the characteristic study were conducted for the SC structure. In addition, FEM as the CV analytical evaluation method was investigated. This report shows the results of experimental analyses and the update of the analytical evaluation method for the SC structure.
Yamamoto, Tomohiko; Kato, Atsushi; Chikazawa, Yoshitaka; Oya, Takeaki*; Iwasaki, Mikinori*; Akiyama, Yo*
no journal, ,
Sodium-cooled Fast Reactor (SFR) is planning to adopt the steel-plate reinforced concrete containment vessel (SCCV). This presentation is the structural integrity and boundary evaluation of SCCV in the hypothetical sodium leakage for construction of safety design criteria (SDC).
Kubo, Shigenobu; Dozaki, Koji*; Oya, Takeaki*
no journal, ,
no abstracts in English
Yamamoto, Tomohiko; Kato, Atsushi; Chikazawa, Yoshitaka; Iwasaki, Mikinori*; Akiyama, Yo*; Oya, Takeaki*
no journal, ,
Japan sodium cooled fast reactor adopts a steel plate reinforced concrete containment vessel (SCCV) with rectangle shape. This reports an evaluation of structural and boundary plate integrity analysis of SCCV in case of sodium combustion.
Kato, Atsushi; Chikazawa, Yoshitaka; Nabeshima, Kunihiko; Iwasaki, Mikinori*; Akiyama, Yo*; Oya, Takeaki*
no journal, ,
This report studies about an enhancement of reactor building layout design against external and human induced events considering features of JSFR (Japan sodium-cooled fast reactor) and 4th generation SFR safety design criteria.
Kato, Atsushi; Chikazawa, Yoshitaka; Nabeshima, Kunihiko; Iwasaki, Mikinori*; Akiyama, Yo*; Oya, Takeaki*
no journal, ,
Based on the Safety design criteria for the Generation-IV sodium cooled fast reactor and intrinsic features of SFR, we studied the reactor building layout design in order to improve its safety.