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Hayafune, Hiroki; Chikazawa, Yoshitaka; Kamide, Hideki; Iwasaki, Mikinori*; Shoji, Takashi*
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 11 Pages, 2017/06
Design studies on a next generation sodium-cooled fast reactor (SFR) considering the safety design criteria (SDC) developed in the generation IV international forum (GIF) was summarized. To meet SDC including the lessons learned from the TEPCO's Fukushima Dai-ichi Nuclear Power Plants accident, the heat removal function was enhanced to avoid loss of the function even if any internal events exceeding design basis or severe external event happen. Several design options have been investigated and auxiliary core cooling system using air as ultimate heat sink has been selected as an additional cooling system regarding system reliability and diversification. Even though the next generation SFR already adopts seismic isolation system, main component designs have been improved considering revised earthquake conditions. For other external events, design measures for various external events are taken into account. Reactor building design has been improved and important safety components are diversified and located separately improving independency. Those design studies and evaluations on the next generation sodium-cooled reactor have contributed to the development of safety design guidelines (SDG) which is under discussion in the GIF framework.
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.
Kamide, Hideki; Ando, Masato*; Ito, Takaya*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05
JAEA, JAPC and MFBR have been conducted design study for the Japan Sodium-cooled Fast Reactor (JSFR), which is a design concept aiming at future commercial use as sustainable electric power source. Since 2011, in order to contribute to the development of safety design criteria (SDC) and safety design guideline (SDG), which include the lesson learned from the TEPCO's Fukushima Dai-ichi Nuclear Power Plants accident, in the frame work of generation IV international forum (GIF), the design study is focusing on the design measures against sever external events such as earthquake and tsunami. At the same time, the design study is going into detail and paying much attention to the maintenance and repair to make surer its feasibility. This paper summarizes the design concept of the demonstration version of JSFR in which progress of design work was incorporated.
Sakamoto, Yoshihiko; Fukasawa, Tsuyoshi*; Kawasaki, Nobuchika; Okamura, Shigeki*
no journal, ,
Design study of an FBR demonstration facility is now in progress for the sodium-cooled fast reactor (JSFR). In JSFR, a seismic isolation system is adopted from the viewpoint of reduction in seismic force to major components taking into account the characteristics of the fast reactor. After the 2011 off the Pacific coast of Tohoku Earthquake, a design earthquake was revised for investigation to ensure seismic resistance under a severer seismic condition. Moreover, countermeasures against various external hazards such as tsunami, etc. were investigated for the purpose of establishment of safety design guidelines and enhancement of safety. This presentation introduces the design earthquake and the seismic isolation system concept responding to the external hazards with issues for realization.
Okano, Yasushi
no journal, ,
The Safety Design Criteria Phase I Report had been issued in 2013, and the following feedbacks from US-NRC, France IRSN, IAEA, and China NNSA are being incorporated for the next issue of the report. The international review on the Safety Approach Safety Design Guideline Report was started in 2016, and the interim feedbacks from the IAEA were provided. The important discussion points and technical backgrounds on these feedbacks will be presented at the session.
Sakai, Takaaki*; Okano, Yasushi; Kubo, Shigenobu; Shimakawa, Yoshio*
no journal, ,
A research committee on Safety Design Guidelines for Generation-IV Sodium-cooled Fast Reactor was formulated and has been working since 2013. Development Approach of Safety Design Guideline, Status of International Review, Development of SDG on Structures, Systems and Components, and Design Concept conformed to Safety Design Guideline are presented as the outcome of the committee.