Investigation on constraint effect of reactor pressure vessel under pressurized thermal shock
In recent years, the integrity of reactor pressure vessels (RPVs) under pressurized thermal shock (PTS) accident has been treated as one of the most critical issues. Under PTS condition, the combination of thermal stress due to a steep temperature gradient and mechanical stress due to internal press...
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| Veröffentlicht in: | Nuclear engineering and design 2003-02, Vol.219 (3), p.197-206 |
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| creator | Kim, Jin-Su Choi, Jae-Boong Kim, Young-Jin Park, Youn-Won |
| description | In recent years, the integrity of reactor pressure vessels (RPVs) under pressurized thermal shock (PTS) accident has been treated as one of the most critical issues. Under PTS condition, the combination of thermal stress due to a steep temperature gradient and mechanical stress due to internal pressure causes considerable tensile stress inside the RPV wall. As a result, cracks on the inner surface of RPVs can experience elastic–plastic behavior that can be explained using the
J-integral. In such a case, however, the
J-integral may possibly lose its validity due to the constraint effect. The degree of constraint effect is influenced by the loading mode, the crack geometry and the material properties. In this paper, three-dimensional finite element analyses are performed for various surface cracks to investigate the effect of clad thickness and crack geometry on the constraint effect. A total of 36 crack geometries are analyzed and results are presented by the two-parameter characterization based on the
J-integral and the
Q-stress. |
| doi_str_mv | 10.1016/S0029-5493(02)00282-0 |
| format | Article |
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J-integral. In such a case, however, the
J-integral may possibly lose its validity due to the constraint effect. The degree of constraint effect is influenced by the loading mode, the crack geometry and the material properties. In this paper, three-dimensional finite element analyses are performed for various surface cracks to investigate the effect of clad thickness and crack geometry on the constraint effect. A total of 36 crack geometries are analyzed and results are presented by the two-parameter characterization based on the
J-integral and the
Q-stress.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/S0029-5493(02)00282-0</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Installations for energy generation and conversion: thermal and electrical energy</subject><ispartof>Nuclear engineering and design, 2003-02, Vol.219 (3), p.197-206</ispartof><rights>2002 Elsevier Science B.V.</rights><rights>2003 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c420t-57a5d5a73d59fe3c3b2bae1ed527ea6eec0752ae31a1b26ff0f6eea3be1326c3</citedby><cites>FETCH-LOGICAL-c420t-57a5d5a73d59fe3c3b2bae1ed527ea6eec0752ae31a1b26ff0f6eea3be1326c3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/S0029-5493(02)00282-0$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3548,27923,27924,45994</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=14416681$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Kim, Jin-Su</creatorcontrib><creatorcontrib>Choi, Jae-Boong</creatorcontrib><creatorcontrib>Kim, Young-Jin</creatorcontrib><creatorcontrib>Park, Youn-Won</creatorcontrib><title>Investigation on constraint effect of reactor pressure vessel under pressurized thermal shock</title><title>Nuclear engineering and design</title><description>In recent years, the integrity of reactor pressure vessels (RPVs) under pressurized thermal shock (PTS) accident has been treated as one of the most critical issues. Under PTS condition, the combination of thermal stress due to a steep temperature gradient and mechanical stress due to internal pressure causes considerable tensile stress inside the RPV wall. As a result, cracks on the inner surface of RPVs can experience elastic–plastic behavior that can be explained using the
J-integral. In such a case, however, the
J-integral may possibly lose its validity due to the constraint effect. The degree of constraint effect is influenced by the loading mode, the crack geometry and the material properties. In this paper, three-dimensional finite element analyses are performed for various surface cracks to investigate the effect of clad thickness and crack geometry on the constraint effect. A total of 36 crack geometries are analyzed and results are presented by the two-parameter characterization based on the
J-integral and the
Q-stress.</description><subject>Applied sciences</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2003</creationdate><recordtype>article</recordtype><recordid>eNqFkE1LAzEQhoMoWKs_QchF0cNqkt3sdk8ixY9CwYM9eJEwm53Y6HZTk92C_npTW-rREAgZnneGeQg55eyKM55fPzMmykRmZXrBxGX8jETC9siAjwqRFLJ82SeDHXJIjkJ4Z-tTigF5nbQrDJ19g866lsarXRs6D7btKBqDuqPOUI-gO-fp0mMIvUcaQwEb2rc17qr2G2vazdEvoKFh7vTHMTkw0AQ82b5DMru_m40fk-nTw2R8O010JliXyAJkLaFIa1kaTHVaiQqQYy1FgZAjalZIAZhy4JXIjWEmFiGtkKci1-mQnG_aLr377OM6amGDxqaBFl0flChKzooyi6DcgNq7EDwatfR2Af5LcabWLtWvS7UWpZhQvy4Vi7mz7QAIGhrjodU2_IWzjOf5iEfuZsNhXHZl0augLbYaa-ujSVU7-8-kH_eri68</recordid><startdate>20030201</startdate><enddate>20030201</enddate><creator>Kim, Jin-Su</creator><creator>Choi, Jae-Boong</creator><creator>Kim, Young-Jin</creator><creator>Park, Youn-Won</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope></search><sort><creationdate>20030201</creationdate><title>Investigation on constraint effect of reactor pressure vessel under pressurized thermal shock</title><author>Kim, Jin-Su ; Choi, Jae-Boong ; Kim, Young-Jin ; Park, Youn-Won</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c420t-57a5d5a73d59fe3c3b2bae1ed527ea6eec0752ae31a1b26ff0f6eea3be1326c3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2003</creationdate><topic>Applied sciences</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kim, Jin-Su</creatorcontrib><creatorcontrib>Choi, Jae-Boong</creatorcontrib><creatorcontrib>Kim, Young-Jin</creatorcontrib><creatorcontrib>Park, Youn-Won</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Kim, Jin-Su</au><au>Choi, Jae-Boong</au><au>Kim, Young-Jin</au><au>Park, Youn-Won</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Investigation on constraint effect of reactor pressure vessel under pressurized thermal shock</atitle><jtitle>Nuclear engineering and design</jtitle><date>2003-02-01</date><risdate>2003</risdate><volume>219</volume><issue>3</issue><spage>197</spage><epage>206</epage><pages>197-206</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>In recent years, the integrity of reactor pressure vessels (RPVs) under pressurized thermal shock (PTS) accident has been treated as one of the most critical issues. Under PTS condition, the combination of thermal stress due to a steep temperature gradient and mechanical stress due to internal pressure causes considerable tensile stress inside the RPV wall. As a result, cracks on the inner surface of RPVs can experience elastic–plastic behavior that can be explained using the
J-integral. In such a case, however, the
J-integral may possibly lose its validity due to the constraint effect. The degree of constraint effect is influenced by the loading mode, the crack geometry and the material properties. In this paper, three-dimensional finite element analyses are performed for various surface cracks to investigate the effect of clad thickness and crack geometry on the constraint effect. A total of 36 crack geometries are analyzed and results are presented by the two-parameter characterization based on the
J-integral and the
Q-stress.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/S0029-5493(02)00282-0</doi><tpages>10</tpages></addata></record> |
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| source | Elsevier ScienceDirect Journals Complete |
| subjects | Applied sciences Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Installations for energy generation and conversion: thermal and electrical energy |
| title | Investigation on constraint effect of reactor pressure vessel under pressurized thermal shock |
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