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Okano, Yasushi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 60(12), p.764 - 769, 2018/12
JAEA has developed the second safety design guidelines report, "Safety Design Guidelines on Structures, Systems and Components" for Generation-IV SFR system, following the previously published SFR Safety Design Criteria and the first SFR Safety Design Guidelines report and with the reviews by a technical committee under Atomic Energy Society of Japan. This article explains about 14 key points on reactor core system, coolant system, and containment system and also current consistency of international SFR designs to the safety design guidelines.
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.
Kubota, Ryuzaburo*; Tani, Akihiro*; Shimakawa, Yoshio*; Kubo, Shigenobu; Okano, Yasushi
no journal, ,
The objective Provision Tree (OPT) methodology was applied for Generation-IV Sodium-cooled Fast Reactor system to analyses challenges and mechanisms for core damage prevention and containment function maintain and to clarify sets of design conditions. The OPT results were utilized to select the list of importance events of JSFR as an example.
Tani, Akihiro*; Shimakawa, Yoshio*; Kubo, Shigenobu; Okano, Yasushi
no journal, ,
The safety design guidelines (SDG) have been developed under the Generation-IV international Forum (GIF) based on the safety design criteria (SDC) for GIF Sodium-cooled Fast Reactors (SFR) and related fundamental safety approaches. An orientation to develop the SDG for structure, system, and component of the SFR is presented in this study. The key design characteristics and requirements evolved from the SDC are discussed as well in comparison with those of the light water reactor system.
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.
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.