Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor
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 tar...
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Veröffentlicht in: | Journal of nuclear science and technology 2011-04, Vol.48 (4), p.463-471 |
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description | 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 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. |
doi_str_mv | 10.1080/18811248.2011.9711720 |
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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 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.</description><identifier>ISSN: 0022-3131</identifier><identifier>EISSN: 1881-1248</identifier><identifier>DOI: 10.1080/18811248.2011.9711720</identifier><identifier>CODEN: JNSTAX</identifier><language>eng</language><publisher>Tokyo: Taylor & Francis Group</publisher><subject>Applied sciences ; commercialization ; demonstration reactor ; design study ; economic performance ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; FaCT ; Fission nuclear power plants ; Fuels ; innovative technologies ; Installations for energy generation and conversion: thermal and electrical energy ; JSFR ; Nuclear fuels ; reliability ; safety</subject><ispartof>Journal of nuclear science and technology, 2011-04, Vol.48 (4), p.463-471</ispartof><rights>Copyright Taylor & Francis Group, LLC 2011</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c387t-9b99082daeea8230d58a27feefd479e4b507602426c94903ead0c28fa01a1acb3</citedby><cites>FETCH-LOGICAL-c387t-9b99082daeea8230d58a27feefd479e4b507602426c94903ead0c28fa01a1acb3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>309,310,314,776,780,785,786,23909,23910,25118,27901,27902</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=24426427$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>AOTO, Kazumi</creatorcontrib><creatorcontrib>UTO, Nariaki</creatorcontrib><creatorcontrib>SAKAMOTO, Yoshihiko</creatorcontrib><creatorcontrib>ITO, Takaya</creatorcontrib><creatorcontrib>TODA, Mikio</creatorcontrib><creatorcontrib>KOTAKE, Shoji</creatorcontrib><title>Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor</title><title>Journal of nuclear science and technology</title><description>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 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.</description><subject>Applied sciences</subject><subject>commercialization</subject><subject>demonstration reactor</subject><subject>design study</subject><subject>economic performance</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>FaCT</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>innovative technologies</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>JSFR</subject><subject>Nuclear fuels</subject><subject>reliability</subject><subject>safety</subject><issn>0022-3131</issn><issn>1881-1248</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2011</creationdate><recordtype>article</recordtype><recordid>eNp9kEtLA0EQhAdRMEZ_gjAXvW3seWR39mZIjA8CStTz0JlHWNnshJkNkn_vLjEePTXdVdUFHyHXDEYMFNwxpRjjUo04MDYqC8YKDidk0N-zXjglAwDOM8EEOycXKX11ay5zNSCTmUvVuqHv7c7uKTaWLm9n9C2GdXQp0dDQF9xipwdb7TbZNITaWTrH1NKlQ9OGeEnOPNbJXf3OIfmcP3xMn7LF6-PzdLLIjFBFm5WrsgTFLTqHiguwY4W88M55K4vSydUYihy45LkpZQnCoQXDlUdgyNCsxJCMD39NDClF5_U2VhuMe81A9xz0kYPuOehfDl3u5pDbYjJY-4iNqdJfmMuuUvKi890ffFXjQ9zgd4i11S3u6xCPIfF_1Q_ybm_x</recordid><startdate>20110401</startdate><enddate>20110401</enddate><creator>AOTO, Kazumi</creator><creator>UTO, Nariaki</creator><creator>SAKAMOTO, Yoshihiko</creator><creator>ITO, Takaya</creator><creator>TODA, Mikio</creator><creator>KOTAKE, Shoji</creator><general>Taylor & Francis Group</general><general>Atomic Energy Society of Japan</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>20110401</creationdate><title>Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor</title><author>AOTO, Kazumi ; UTO, Nariaki ; SAKAMOTO, Yoshihiko ; ITO, Takaya ; TODA, Mikio ; KOTAKE, Shoji</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c387t-9b99082daeea8230d58a27feefd479e4b507602426c94903ead0c28fa01a1acb3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2011</creationdate><topic>Applied sciences</topic><topic>commercialization</topic><topic>demonstration reactor</topic><topic>design study</topic><topic>economic performance</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>FaCT</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>innovative technologies</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>JSFR</topic><topic>Nuclear fuels</topic><topic>reliability</topic><topic>safety</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>AOTO, Kazumi</creatorcontrib><creatorcontrib>UTO, Nariaki</creatorcontrib><creatorcontrib>SAKAMOTO, Yoshihiko</creatorcontrib><creatorcontrib>ITO, Takaya</creatorcontrib><creatorcontrib>TODA, Mikio</creatorcontrib><creatorcontrib>KOTAKE, Shoji</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><jtitle>Journal of nuclear science and technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>AOTO, Kazumi</au><au>UTO, Nariaki</au><au>SAKAMOTO, Yoshihiko</au><au>ITO, Takaya</au><au>TODA, Mikio</au><au>KOTAKE, Shoji</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor</atitle><jtitle>Journal of nuclear science and technology</jtitle><date>2011-04-01</date><risdate>2011</risdate><volume>48</volume><issue>4</issue><spage>463</spage><epage>471</epage><pages>463-471</pages><issn>0022-3131</issn><eissn>1881-1248</eissn><coden>JNSTAX</coden><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 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.</abstract><cop>Tokyo</cop><pub>Taylor & Francis Group</pub><doi>10.1080/18811248.2011.9711720</doi><tpages>9</tpages><oa>free_for_read</oa></addata></record> |
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source | EZB-FREE-00999 freely available EZB journals; Alma/SFX Local Collection; Free Full-Text Journals in Chemistry |
subjects | Applied sciences commercialization demonstration reactor design study economic performance Energy Energy. Thermal use of fuels Exact sciences and technology FaCT Fission nuclear power plants Fuels innovative technologies Installations for energy generation and conversion: thermal and electrical energy JSFR Nuclear fuels reliability safety |
title | Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor |
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