Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor
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In this paper, 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 is described.Abstract:
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 1,500MWe is targeted for commercialization at around 2050, and a demonstration reactor assuming a power output from 500 to 750MWe 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...read more
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References
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Journal ArticleDOI
A next generation sodium-cooled fast reactor concept and its r&d program
TL;DR: A promising design concept of sodium-cooled fast reactor JSFR is proposed aiming at fully satisfaction of the development targets for the next generation nuclear energy system in this article, where a roadmap toward JSFR commercialization is described, to be followed up in a new framework of the Fast reactor Cycle Technology development(FaCT) Project launched in 2006.
Journal ArticleDOI
Development of advanced loop-type fast reactor in japan
Shoji Kotake,Yoshihiko Sakamoto,Takatsugu Mihara,Shigenobu Kubo,Nariaki Uto,Yoshio Kamishima,Kazumi Aoto,Mikio Toda +7 more
TL;DR: In this article, the current status of the design study and related research and development for an advanced loop-type fast reactor: the Japan sodium-cooled fast reactor (JSFR).
Proceedings ArticleDOI
Evaluation of Creep Strength Reduction Factors for Welded Joints of Modified 9Cr-1Mo Steel (P91)
Masaaki Tabuchi,Yukio Takahashi +1 more
Abstract: In order to review the allowable creep strength of high Cr ferritic steels, creep rupture data of base metal and welded joints have been collected and long-term creep strength have been analyzed in the SHC committee in Japan since 2004. In the present paper, the creep rupture data of 370 points for welded joint specimens of modified 9Cr-1Mo steel (ASME Grade 91) offered from seven Japanese companies and institutes were analyzed. These data clearly indicated that the creep strength of welded joints was lower than that of base metal due to Type IV fracture in HAZ at or above 600°C. From the activities of this committee, the master curve for life evaluation of welded joints of Gr.91 steel could be represented as follows: LMP==34154+3494(log σ)−2574(log σ)2, C=31.4 The reduction factor of 100,000 hours creep rupture strength of welded joint to base metal was concluded to be 0.75 at 600°C and 0.70 at 650°C for the Gr.91 steel.Copyright © 2006 by ASME
Journal ArticleDOI
Seismic Isolation Design for JSFR
Shigeki Okamura,Yoshio Kamishima,Kazuo Negishi,Yoshihiko Sakamoto,Seiji Kitamura,Shoji Kotake +5 more
TL;DR: In this paper, the authors describe 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.
Journal ArticleDOI
Analytical study on elimination of severe recriticalities in large scale LMFBRS with enhancement of fuel discharge
TL;DR: In this paper, modified-FAIDUS (fuel subassembly with inner DUct structure) is proposed to enhance the fuel discharge from core in order to prevent formation of the core-wide molten pool with high mobility.