This paper describes the progress of the design study and research and development (R&D) for the Japan Sodium-cooled Fast Reactor (JSFR) implemented in the ''Fast Reactor Cycle Technology Development (FaCT)'' project. A sodium-cooled fast reactor with an electric power of 1,500 MWe is targeted for commercialization at around 2050, and a demonstration reactor assuming a power output from 500 to 750 MWe is planned to start operation at around 2025. R&D on innovative technologies to achieve economic competitiveness and enhance reliability and safety is carried out for the commercialization. A compact reactor vessel without a vessel wall cooling system is pursued in consideration of the wall thickness enough to resist the severest seismic condition. A two-loop cooling system with shortened highchromium steel piping is a crucial feature, and studies on the hydraulics in the pipe elbow and the fabrication capability of the pipes are being carried out. A double-walled straight tube steam generator is investigated to enhance the reliability against sodium/water reaction, and developmental works are progressing, including the thermal-hydraulic design and trial manufacturing for components. Self-Actuated Shutdown System (SASS) is being developed with safety analysis of the applicability for JSFR and experimental demonstration in the experimental fast reactor JOYO. An advanced fuel handling system is pursued to enhance economic performance. In parallel with considering the necessity of studies on alternative technologies, discussion on whether the innovative technologies can be adopted for JSFR is in progress to be finalized in 2010.
This paper describes the seismic design of Japan Sodium-Cooled Fast Reactor (JSFR), which includes the seismic condition, the seismic isolation system, and the seismic evaluation of the primary components. Since the design seismic loading is set out severely than ever since The Niigata-ken Chuetsu-oki Earthquake in 2007, an advanced seismic isolation system is aimed to reduce the seismic force loaded on the primary components of JSFR to be less than that of the previous seismic isolation system. The advanced seismic isolation system is developed by optimizing the performance based on the previous seismic isolation system considering the natural frequency of the primary components. The laminated rubber bearings thicker than the previous ones and oil dampers are adopted for the advanced seismic isolation system of SFR. The seismic evaluation of nuclear reactor components applying the advanced seismic isolation system is performed and its feasibility is confirmed.
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