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An evaluation of a direct cooling method for the ex-vessel corium stabilization
► An ex-vessel core catcher system of sample advanced light water reactor is evaluated. ► The coolant mixture of water and gas is injected from bottom of the core catcher. ► We analyze accident scenario, spreading, cooling history, and containment pressure. ► Several cases with change of water and g...
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Published in: | Nuclear engineering and design 2011-12, Vol.241 (12), p.4737-4744 |
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creator | Ha, Kwang Soon Kim, Hwan Yeol Kim, Jongtae Park, Jong Hwa |
description | ► An ex-vessel core catcher system of sample advanced light water reactor is evaluated. ► The coolant mixture of water and gas is injected from bottom of the core catcher. ► We analyze accident scenario, spreading, cooling history, and containment pressure. ► Several cases with change of water and gas injection rates are calculated. ► It is confirmed that the bottom water/gas injection system is effective.
An evaluation of the ex-vessel core catcher system of a sample advanced light water reactor was presented. The core catcher was designed to cool down the molten corium through a combined injection of water and gas from the bottom of the molten corium, which could be effective in the reduction of rapid steam generation. By using the MELCOR code, a scenario analysis was performed for a representative severe accident scenario of the ALWR, that is, the 6-in. large break loss of coolant accident without safe injection. The spreading characteristics of ejected corium at vessel breach were asymptotically evaluated on the core catcher horizontal surface. The composition of the molten corium, the decay power level, and the sacrificial concrete ablation depth with time were obtained by a sacrificial concrete ablation analysis. The corium cooling history in the core catcher during the coolant injection was evaluated to calculate the temporal steam generation rate by considering an energy conservation equation. These were used as the major inputs for the temporal calculations of containment pressure which was performed by using the GASFLOW code. Several cases with change of water and gas injection rates were calculated. It was confirmed that the bottom water/gas injection system was an effective corium cooling method in the ex-vessel core catcher to suppress the quick release of steam. |
doi_str_mv | 10.1016/j.nucengdes.2011.03.033 |
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An evaluation of the ex-vessel core catcher system of a sample advanced light water reactor was presented. The core catcher was designed to cool down the molten corium through a combined injection of water and gas from the bottom of the molten corium, which could be effective in the reduction of rapid steam generation. By using the MELCOR code, a scenario analysis was performed for a representative severe accident scenario of the ALWR, that is, the 6-in. large break loss of coolant accident without safe injection. The spreading characteristics of ejected corium at vessel breach were asymptotically evaluated on the core catcher horizontal surface. The composition of the molten corium, the decay power level, and the sacrificial concrete ablation depth with time were obtained by a sacrificial concrete ablation analysis. The corium cooling history in the core catcher during the coolant injection was evaluated to calculate the temporal steam generation rate by considering an energy conservation equation. These were used as the major inputs for the temporal calculations of containment pressure which was performed by using the GASFLOW code. Several cases with change of water and gas injection rates were calculated. It was confirmed that the bottom water/gas injection system was an effective corium cooling method in the ex-vessel core catcher to suppress the quick release of steam.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2011.03.033</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Ablation ; Applied sciences ; Catchers ; Concretes ; Controled nuclear fusion plants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fuels ; Gas injection ; Installations for energy generation and conversion: thermal and electrical energy ; Mathematical analysis ; Nuclear fuels ; Nuclear power generation ; Steam electric power generation ; Steam generation</subject><ispartof>Nuclear engineering and design, 2011-12, Vol.241 (12), p.4737-4744</ispartof><rights>2011 Elsevier B.V.</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c410t-9dc4343d936584c04a107d8470b24d8e27e131ca4c06b647abd1b6d613f8bf8d3</citedby><cites>FETCH-LOGICAL-c410t-9dc4343d936584c04a107d8470b24d8e27e131ca4c06b647abd1b6d613f8bf8d3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>309,310,314,780,784,789,790,23930,23931,25140,27924,27925</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=25312543$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Ha, Kwang Soon</creatorcontrib><creatorcontrib>Kim, Hwan Yeol</creatorcontrib><creatorcontrib>Kim, Jongtae</creatorcontrib><creatorcontrib>Park, Jong Hwa</creatorcontrib><title>An evaluation of a direct cooling method for the ex-vessel corium stabilization</title><title>Nuclear engineering and design</title><description>► An ex-vessel core catcher system of sample advanced light water reactor is evaluated. ► The coolant mixture of water and gas is injected from bottom of the core catcher. ► We analyze accident scenario, spreading, cooling history, and containment pressure. ► Several cases with change of water and gas injection rates are calculated. ► It is confirmed that the bottom water/gas injection system is effective.
An evaluation of the ex-vessel core catcher system of a sample advanced light water reactor was presented. The core catcher was designed to cool down the molten corium through a combined injection of water and gas from the bottom of the molten corium, which could be effective in the reduction of rapid steam generation. By using the MELCOR code, a scenario analysis was performed for a representative severe accident scenario of the ALWR, that is, the 6-in. large break loss of coolant accident without safe injection. The spreading characteristics of ejected corium at vessel breach were asymptotically evaluated on the core catcher horizontal surface. The composition of the molten corium, the decay power level, and the sacrificial concrete ablation depth with time were obtained by a sacrificial concrete ablation analysis. The corium cooling history in the core catcher during the coolant injection was evaluated to calculate the temporal steam generation rate by considering an energy conservation equation. These were used as the major inputs for the temporal calculations of containment pressure which was performed by using the GASFLOW code. Several cases with change of water and gas injection rates were calculated. It was confirmed that the bottom water/gas injection system was an effective corium cooling method in the ex-vessel core catcher to suppress the quick release of steam.</description><subject>Ablation</subject><subject>Applied sciences</subject><subject>Catchers</subject><subject>Concretes</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Gas injection</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Mathematical analysis</subject><subject>Nuclear fuels</subject><subject>Nuclear power generation</subject><subject>Steam electric power generation</subject><subject>Steam generation</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2011</creationdate><recordtype>article</recordtype><recordid>eNqFkE1LAzEQhoMoWKu_wVxEL1vztZvdYyl-QaEXBW8hm8zWlO1Gk92i_npTW3rUYWAO88y88CB0ScmEElrcribdYKBbWogTRiidEJ6aH6ERLSXLZF69HqMRIazKclHxU3QW44psq2IjtJh2GDa6HXTvfId9gzW2LoDpsfG-dd0Sr6F_8xY3PuD-DTB8ZhuIEdoEBDescex17Vr3_fvhHJ00uo1wsZ9j9HJ_9zx7zOaLh6fZdJ4ZQUmfVdYILriteJGXwhChKZG2FJLUTNgSmATKqdFpVdSFkLq2tC5sQXlT1k1p-Rhd7_6-B_8xQOzV2kUDbas78ENUFeOMsKIsEnnzJ0mllCm8EnlC5Q41wccYoFHvwa11-FKUqK1stVIH2WorWxGemqfLq32Ijka3TdCdcfFwznJOWS623HTHQXKzcRBUNA46Azvnynr3b9YPyJ6ZFw</recordid><startdate>20111201</startdate><enddate>20111201</enddate><creator>Ha, Kwang Soon</creator><creator>Kim, Hwan Yeol</creator><creator>Kim, Jongtae</creator><creator>Park, Jong Hwa</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><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><scope>7ST</scope><scope>7U6</scope></search><sort><creationdate>20111201</creationdate><title>An evaluation of a direct cooling method for the ex-vessel corium stabilization</title><author>Ha, Kwang Soon ; Kim, Hwan Yeol ; Kim, Jongtae ; Park, Jong Hwa</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c410t-9dc4343d936584c04a107d8470b24d8e27e131ca4c06b647abd1b6d613f8bf8d3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2011</creationdate><topic>Ablation</topic><topic>Applied sciences</topic><topic>Catchers</topic><topic>Concretes</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. 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An evaluation of the ex-vessel core catcher system of a sample advanced light water reactor was presented. The core catcher was designed to cool down the molten corium through a combined injection of water and gas from the bottom of the molten corium, which could be effective in the reduction of rapid steam generation. By using the MELCOR code, a scenario analysis was performed for a representative severe accident scenario of the ALWR, that is, the 6-in. large break loss of coolant accident without safe injection. The spreading characteristics of ejected corium at vessel breach were asymptotically evaluated on the core catcher horizontal surface. The composition of the molten corium, the decay power level, and the sacrificial concrete ablation depth with time were obtained by a sacrificial concrete ablation analysis. The corium cooling history in the core catcher during the coolant injection was evaluated to calculate the temporal steam generation rate by considering an energy conservation equation. These were used as the major inputs for the temporal calculations of containment pressure which was performed by using the GASFLOW code. Several cases with change of water and gas injection rates were calculated. It was confirmed that the bottom water/gas injection system was an effective corium cooling method in the ex-vessel core catcher to suppress the quick release of steam.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2011.03.033</doi><tpages>8</tpages></addata></record> |
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subjects | Ablation Applied sciences Catchers Concretes Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Gas injection Installations for energy generation and conversion: thermal and electrical energy Mathematical analysis Nuclear fuels Nuclear power generation Steam electric power generation Steam generation |
title | An evaluation of a direct cooling method for the ex-vessel corium stabilization |
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