Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea
Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for e...
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Veröffentlicht in: | Science and Technology of Nuclear Installations 2013-01, Vol.2013 (2013), p.1-18 |
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creator | Chang, Jinwook Lee, Yong Bum Lee, Chan Bock Choi, Chiwoong Kim, Yeong-il |
description | Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for electricity generation, because it can utilize efficiently uranium resources and reduce radioactive waste. Acknowledging the importance of a fast reactor in a future energy policy, the long-term advanced SFR development plan was authorized by KAEC in 2008 and updated in 2011 which will be carried out toward the construction of an advanced SFR prototype plant by 2028. Based upon the experiences gained during the development of the conceptual designs for KALIMER, KAERI recently developed advanced sodium-cooled fast reactor (SFR) design concepts of TRU burner that can better meet the generation IV technology goals. The current status of nuclear power and SFR design technology development program in Korea will be discussed. The developments of design concepts including core, fuel, fluid system, mechanical structure, and safety evaluation have been performed. In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities. |
doi_str_mv | 10.1155/2013/290362 |
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The developments of design concepts including core, fuel, fluid system, mechanical structure, and safety evaluation have been performed. In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities.</description><identifier>ISSN: 1687-6075</identifier><identifier>EISSN: 1687-6083</identifier><identifier>DOI: 10.1155/2013/290362</identifier><language>eng</language><publisher>Cairo, Egypt: Hindawi Puplishing Corporation</publisher><subject>Design and construction ; Engineering design ; Methods ; Nuclear reactors</subject><ispartof>Science and Technology of Nuclear Installations, 2013-01, Vol.2013 (2013), p.1-18</ispartof><rights>Copyright © 2013 Yeong-il Kim et al.</rights><rights>COPYRIGHT 2013 John Wiley & Sons, Inc.</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c400t-a47fa9a58e657e728ca2487abdc0b15348499aae2d580fff119125c4a52802b43</citedby><cites>FETCH-LOGICAL-c400t-a47fa9a58e657e728ca2487abdc0b15348499aae2d580fff119125c4a52802b43</cites><orcidid>0000-0002-3904-4620</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,864,877,27924,27925</link.rule.ids></links><search><contributor>Shen, Wei</contributor><creatorcontrib>Chang, Jinwook</creatorcontrib><creatorcontrib>Lee, Yong Bum</creatorcontrib><creatorcontrib>Lee, Chan Bock</creatorcontrib><creatorcontrib>Choi, Chiwoong</creatorcontrib><creatorcontrib>Kim, Yeong-il</creatorcontrib><title>Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea</title><title>Science and Technology of Nuclear Installations</title><description>Korea imports about 97% of its energy resources due to a lack of available energy resources. 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In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities.</description><subject>Design and construction</subject><subject>Engineering design</subject><subject>Methods</subject><subject>Nuclear reactors</subject><issn>1687-6075</issn><issn>1687-6083</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2013</creationdate><recordtype>article</recordtype><sourceid>RHX</sourceid><recordid>eNqFkUtLw0AQx4MoWGpPnoU9CSqpu5vdZHMsqdViUWj1HCb7qAtptmRTH9_eLZFCTzKHef1mBv4TRZcEjwnh_J5iktzTHCcpPYkGJBVZnGKRnB7ijJ9HI-9thRnLUsxIPoheptrbdYMK10i97ZAzaKI-ISQKrZyyu01cOFeHbAa-Q0sNsnMtgkaFuIYuNJbXU2Qb9OxaDRfRmYHa69GfH0bvs4e34ilevD7Oi8kilgzjLgaWGciBC53yTGdUSKBMZFApiSvCEyZYngNoqrjAxhhCckK5ZMCpwLRiyTAa93vXUOvSNsZ1LchgSm-sdI02NtQnSZanDCeMh4Gbo4HAdPq7W8PO-3K-Wh6zdz0rW-d9q025be0G2p-S4HIvdbmXuuylDvRtT3_YRsGX_Qe-6mEdEG3gALPwnnD9F83tg9A</recordid><startdate>20130101</startdate><enddate>20130101</enddate><creator>Chang, Jinwook</creator><creator>Lee, Yong Bum</creator><creator>Lee, Chan Bock</creator><creator>Choi, Chiwoong</creator><creator>Kim, Yeong-il</creator><general>Hindawi Puplishing Corporation</general><general>Hindawi Publishing Corporation</general><general>John Wiley & Sons, Inc</general><scope>ADJCN</scope><scope>AGBXD</scope><scope>AHFXO</scope><scope>RHU</scope><scope>RHW</scope><scope>RHX</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>ISR</scope><orcidid>https://orcid.org/0000-0002-3904-4620</orcidid></search><sort><creationdate>20130101</creationdate><title>Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea</title><author>Chang, Jinwook ; Lee, Yong Bum ; Lee, Chan Bock ; Choi, Chiwoong ; Kim, Yeong-il</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c400t-a47fa9a58e657e728ca2487abdc0b15348499aae2d580fff119125c4a52802b43</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2013</creationdate><topic>Design and construction</topic><topic>Engineering design</topic><topic>Methods</topic><topic>Nuclear reactors</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Chang, Jinwook</creatorcontrib><creatorcontrib>Lee, Yong Bum</creatorcontrib><creatorcontrib>Lee, Chan Bock</creatorcontrib><creatorcontrib>Choi, Chiwoong</creatorcontrib><creatorcontrib>Kim, Yeong-il</creatorcontrib><collection>الدوريات العلمية والإحصائية - e-Marefa Academic and Statistical Periodicals</collection><collection>قاعدة البيئة والطاقة والمياه - e-Marefa Water, Energy & Environment Issues</collection><collection>معرفة - المحتوى العربي الأكاديمي المتكامل - e-Marefa Academic Complete</collection><collection>Hindawi Publishing Complete</collection><collection>Hindawi Publishing Subscription Journals</collection><collection>Hindawi Publishing Open Access</collection><collection>CrossRef</collection><collection>Gale In Context: Science</collection><jtitle>Science and Technology of Nuclear Installations</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Chang, Jinwook</au><au>Lee, Yong Bum</au><au>Lee, Chan Bock</au><au>Choi, Chiwoong</au><au>Kim, Yeong-il</au><au>Shen, Wei</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea</atitle><jtitle>Science and Technology of Nuclear Installations</jtitle><date>2013-01-01</date><risdate>2013</risdate><volume>2013</volume><issue>2013</issue><spage>1</spage><epage>18</epage><pages>1-18</pages><issn>1687-6075</issn><eissn>1687-6083</eissn><abstract>Korea imports about 97% of its energy resources due to a lack of available energy resources. 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source | DOAJ Directory of Open Access Journals; Wiley_OA刊; EZB-FREE-00999 freely available EZB journals; Alma/SFX Local Collection |
subjects | Design and construction Engineering design Methods Nuclear reactors |
title | Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea |
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