Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code
A LBLOCA scenario for an advanced pressurized water reactor, call APR1400, developed in Korea is analyzed in order to obtain an overall insight into a severe accident progression from an initiating event to the reactor vessel failure in detail by using the MELCOR computer code Versions 1.8.5 and 1.8...
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Veröffentlicht in: | Nuclear engineering and design 2014-04, Vol.269, p.155-159 |
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creator | Kim, Tae Woon Song, Jinho Huong, Vo Thi Kim, Dong Ha Rhee, Bo Wook Revankar, Shripad |
description | A LBLOCA scenario for an advanced pressurized water reactor, call APR1400, developed in Korea is analyzed in order to obtain an overall insight into a severe accident progression from an initiating event to the reactor vessel failure in detail by using the MELCOR computer code Versions 1.8.5 and 1.8.6. The present results (the amount of molten corium and vessel failure timing) would be used as input for the establishment of severe accident management strategies or for the design of a core catcher for the APR1400. The MELCOR results showed that the lower head instrumentation tube penetration failure model and internal structure in the reactor vessel had influence on the amount of corium ejected and the timing of reactor vessel failure. |
doi_str_mv | 10.1016/j.nucengdes.2013.08.022 |
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The present results (the amount of molten corium and vessel failure timing) would be used as input for the establishment of severe accident management strategies or for the design of a core catcher for the APR1400. The MELCOR results showed that the lower head instrumentation tube penetration failure model and internal structure in the reactor vessel had influence on the amount of corium ejected and the timing of reactor vessel failure.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2013.08.022</identifier><language>eng</language><publisher>Elsevier B.V</publisher><subject>Accident analysis ; Accidents ; Failure ; Nuclear reactor components ; Nuclear reactors ; Pressurized water reactors ; Progressions ; Time measurements</subject><ispartof>Nuclear engineering and design, 2014-04, Vol.269, p.155-159</ispartof><rights>2013 Elsevier B.V.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c348t-d0390af91a8cb98fc009c864ebcaef97be388d6fde34ab9ec91bd6c7940ce6ab3</citedby></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.nucengdes.2013.08.022$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3548,27922,27923,45993</link.rule.ids></links><search><creatorcontrib>Kim, Tae Woon</creatorcontrib><creatorcontrib>Song, Jinho</creatorcontrib><creatorcontrib>Huong, Vo Thi</creatorcontrib><creatorcontrib>Kim, Dong Ha</creatorcontrib><creatorcontrib>Rhee, Bo Wook</creatorcontrib><creatorcontrib>Revankar, Shripad</creatorcontrib><title>Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code</title><title>Nuclear engineering and design</title><description>A LBLOCA scenario for an advanced pressurized water reactor, call APR1400, developed in Korea is analyzed in order to obtain an overall insight into a severe accident progression from an initiating event to the reactor vessel failure in detail by using the MELCOR computer code Versions 1.8.5 and 1.8.6. The present results (the amount of molten corium and vessel failure timing) would be used as input for the establishment of severe accident management strategies or for the design of a core catcher for the APR1400. The MELCOR results showed that the lower head instrumentation tube penetration failure model and internal structure in the reactor vessel had influence on the amount of corium ejected and the timing of reactor vessel failure.</description><subject>Accident analysis</subject><subject>Accidents</subject><subject>Failure</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Pressurized water reactors</subject><subject>Progressions</subject><subject>Time measurements</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2014</creationdate><recordtype>article</recordtype><recordid>eNqFkM1LAzEQxYMoWKt_gzl62TXZ7EdyLKV-QEWpil4kZCezJaXdrcluof-9KRWvzmUYeO8x70fINWcpZ7y8XaXtANguLYY0Y1ykTKYsy07IiMsqS6pCfZ6SEWOZSopciXNyEcKKHUZlI_L1im1wvdu5fk9DP9g97VoacIceqQFwFtueQhevDa57uvXd0mMILqqazlNjd6YFtPTlY0GH4NolfZrNp8-L6LF4Sc4asw549bvH5P1u9jZ9SObP94_TyTwBkcs-sUwoZhrFjYRayQbibyDLHGsw2KiqRiGlLRuLIje1QlC8tiVUKmeApanFmNwcc-N73wOGXm9cAFyvTYvdEDQvClXKQggVpdVRCr4LwWOjt95tjN9rzvQBqF7pP6D6AFQzqSPQ6JwcnRib7Bx6HcDhobzzCL22nfs34wds74V8</recordid><startdate>20140401</startdate><enddate>20140401</enddate><creator>Kim, Tae Woon</creator><creator>Song, Jinho</creator><creator>Huong, Vo Thi</creator><creator>Kim, Dong Ha</creator><creator>Rhee, Bo Wook</creator><creator>Revankar, Shripad</creator><general>Elsevier B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7SU</scope><scope>7TB</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20140401</creationdate><title>Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code</title><author>Kim, Tae Woon ; Song, Jinho ; Huong, Vo Thi ; Kim, Dong Ha ; Rhee, Bo Wook ; Revankar, Shripad</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c348t-d0390af91a8cb98fc009c864ebcaef97be388d6fde34ab9ec91bd6c7940ce6ab3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2014</creationdate><topic>Accident analysis</topic><topic>Accidents</topic><topic>Failure</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Pressurized water reactors</topic><topic>Progressions</topic><topic>Time measurements</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kim, Tae Woon</creatorcontrib><creatorcontrib>Song, Jinho</creatorcontrib><creatorcontrib>Huong, Vo Thi</creatorcontrib><creatorcontrib>Kim, Dong Ha</creatorcontrib><creatorcontrib>Rhee, Bo Wook</creatorcontrib><creatorcontrib>Revankar, Shripad</creatorcontrib><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Environmental Engineering Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Kim, Tae Woon</au><au>Song, Jinho</au><au>Huong, Vo Thi</au><au>Kim, Dong Ha</au><au>Rhee, Bo Wook</au><au>Revankar, Shripad</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code</atitle><jtitle>Nuclear engineering and design</jtitle><date>2014-04-01</date><risdate>2014</risdate><volume>269</volume><spage>155</spage><epage>159</epage><pages>155-159</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><abstract>A LBLOCA scenario for an advanced pressurized water reactor, call APR1400, developed in Korea is analyzed in order to obtain an overall insight into a severe accident progression from an initiating event to the reactor vessel failure in detail by using the MELCOR computer code Versions 1.8.5 and 1.8.6. 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subjects | Accident analysis Accidents Failure Nuclear reactor components Nuclear reactors Pressurized water reactors Progressions Time measurements |
title | Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code |
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