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久保 重信
no journal, ,
This paper describes AM (Accident Management) measures for JSFR (Japan Sodium-cooled Fast Reactor). And the applicability of IAEA SSG-54 Accident Management Programmes for Nuclear Power Plants will be discussed based on that. The JSFR, which is a conceptual SFR aiming at commercial use, covers power range of medium to large to satisfy its needs as sustainable base-load power supply. The safety approach was developed from the basis of that of Joyo and Monju and advanced features for prevention and mitigation of core damage are incorporated as built-in manner. The safety design for SFR has been implemented corresponding to the characteristics utilizing sodium as coolant and as fast neutron critical system. Moreover, taking lessons from the Fukushima Dai-ichi accident, safety improvement has been carried out to withstand severe conditions such as immense earthquake, tsunami, and long-term station blackout.
栗坂 健一
no journal, ,
The purpose of this presentation is to provide practical examples in the development of accident management programmes for advanced reactors. As part of development of sodium-cooled fast reactor (SFR) in Japan, JAEA developed the prototype SFR. To enhance the provisions in defense-in-depth (DiD) level 4, accident management (AM) measures of the prototype SFR in Japan were studied and developed. The scope of topics is focused on AM measures for prevention of core damage. Fundamental safety functions of the prototype SFR are (1) reactor shutdown, (2) maintaining reactor coolant level, and (3) decay heat removal. For each safety function, challenge mechanisms, plant vulnerabilities, and plant capabilities were considered in the AM development process. Representative AM measures for the safety functions are (1) de-energizing the control rod holding electromagnet, (2) siphon-break of the leak path against second leak in the primary heat transport system, and (3) switching to natural circulation cooling.