Optimum local failure model of steam generator tubes with multiple axial through-wall cracks
It is commonly required that steam generator tubes wall-thinned in excess of 40% should be plugged. However, the plugging criteria are known to be too conservative for some locations and types of defects and its application is confined to a single crack. In the previous study, a crack coalescence mo...
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Veröffentlicht in: | Nuclear engineering and design 2005-08, Vol.235 (17), p.2099-2108 |
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creator | Moon, Seong In Kim, Young Jin Lee, Jin Ho Park, Youn Won Song, Myung Ho |
description | It is commonly required that steam generator tubes wall-thinned in excess of 40% should be plugged. However, the plugging criteria are known to be too conservative for some locations and types of defects and its application is confined to a single crack. In the previous study, a crack coalescence model applicable to steam generator tubes with two collinear axial through-wall cracks was proposed and a coalescence evaluation diagram was developed which can be used to determine whether the adjacent cracks detected by NDE coalesce or not. In this paper, a total of 9 local failure models including flow stress model, necking-based model, stress-based model, reaction force model and plastic zone contact model were introduced to determine the optimum local failure model. Plastic collapse tests and finite element analyses using thin plates with two collinear through-wall cracks were performed for the selection of the optimum local failure model. By comparing the test results with the prediction results obtained from local failure models, the reaction force model and plastic zone contact model were determined as the optimum local failure models. |
doi_str_mv | 10.1016/j.nucengdes.2005.05.024 |
format | Article |
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However, the plugging criteria are known to be too conservative for some locations and types of defects and its application is confined to a single crack. In the previous study, a crack coalescence model applicable to steam generator tubes with two collinear axial through-wall cracks was proposed and a coalescence evaluation diagram was developed which can be used to determine whether the adjacent cracks detected by NDE coalesce or not. In this paper, a total of 9 local failure models including flow stress model, necking-based model, stress-based model, reaction force model and plastic zone contact model were introduced to determine the optimum local failure model. Plastic collapse tests and finite element analyses using thin plates with two collinear through-wall cracks were performed for the selection of the optimum local failure model. By comparing the test results with the prediction results obtained from local failure models, the reaction force model and plastic zone contact model were determined as the optimum local failure models.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2005.05.024</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. 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However, the plugging criteria are known to be too conservative for some locations and types of defects and its application is confined to a single crack. In the previous study, a crack coalescence model applicable to steam generator tubes with two collinear axial through-wall cracks was proposed and a coalescence evaluation diagram was developed which can be used to determine whether the adjacent cracks detected by NDE coalesce or not. In this paper, a total of 9 local failure models including flow stress model, necking-based model, stress-based model, reaction force model and plastic zone contact model were introduced to determine the optimum local failure model. Plastic collapse tests and finite element analyses using thin plates with two collinear through-wall cracks were performed for the selection of the optimum local failure model. By comparing the test results with the prediction results obtained from local failure models, the reaction force model and plastic zone contact model were determined as the optimum local failure models.</description><subject>Applied sciences</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>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Nuclear fuels</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2005</creationdate><recordtype>article</recordtype><recordid>eNqFUMtKxDAUDaLg-PgGs9Fdax5N0y6HwRcIbhRcCCGT3s5kTJsxSX38vS0juvRy4N7FOfdwDkJnlOSU0PJyk_eDgX7VQMwZISKfwIo9NKOVZJkU9fM-mhHC6kwUNT9ERzFuyDQ1m6GXh22y3dBh5412uNXWDQFw5xtw2Lc4JtAdXkEPQScfcBqWEPGHTWvcDS7ZrQOsP-0oTevgh9U6-9DOYRO0eY0n6KDVLsLpzz5GT9dXj4vb7P7h5m4xv88Ml2XKZCOkqUQjGa-l1AWtCtEQKWu6XNZStwRaykkzpgFpQAg-HnUp-VIwrjWV_Bhd7P5ug38bICbV2WjAOd2DH6JiFRGsFMVIlDuiCT7GAK3aBtvp8KUoUVObaqN-21RTm2oCm5TnPxY6jkW1QffGxj-5JKKsOB158x0PxrzvFoKKxkJvoLEBTFKNt_96fQNjM4_t</recordid><startdate>20050801</startdate><enddate>20050801</enddate><creator>Moon, Seong In</creator><creator>Kim, Young Jin</creator><creator>Lee, Jin Ho</creator><creator>Park, Youn Won</creator><creator>Song, Myung Ho</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SC</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>JQ2</scope><scope>KR7</scope><scope>L7M</scope><scope>L~C</scope><scope>L~D</scope></search><sort><creationdate>20050801</creationdate><title>Optimum local failure model of steam generator tubes with multiple axial through-wall cracks</title><author>Moon, Seong In ; Kim, Young Jin ; Lee, Jin Ho ; Park, Youn Won ; Song, Myung Ho</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c376t-7d57c85d723977a41845d07791bb97af0ef130d872e7ce55372e9673b523aa173</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2005</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Nuclear fuels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Moon, Seong In</creatorcontrib><creatorcontrib>Kim, Young Jin</creatorcontrib><creatorcontrib>Lee, Jin Ho</creatorcontrib><creatorcontrib>Park, Youn Won</creatorcontrib><creatorcontrib>Song, Myung Ho</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Computer and Information Systems Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>ProQuest Computer Science Collection</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Computer and Information Systems Abstracts Academic</collection><collection>Computer and Information Systems Abstracts Professional</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Moon, Seong In</au><au>Kim, Young Jin</au><au>Lee, Jin Ho</au><au>Park, Youn Won</au><au>Song, Myung Ho</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Optimum local failure model of steam generator tubes with multiple axial through-wall cracks</atitle><jtitle>Nuclear engineering and design</jtitle><date>2005-08-01</date><risdate>2005</risdate><volume>235</volume><issue>17</issue><spage>2099</spage><epage>2108</epage><pages>2099-2108</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>It is commonly required that steam generator tubes wall-thinned in excess of 40% should be plugged. However, the plugging criteria are known to be too conservative for some locations and types of defects and its application is confined to a single crack. In the previous study, a crack coalescence model applicable to steam generator tubes with two collinear axial through-wall cracks was proposed and a coalescence evaluation diagram was developed which can be used to determine whether the adjacent cracks detected by NDE coalesce or not. In this paper, a total of 9 local failure models including flow stress model, necking-based model, stress-based model, reaction force model and plastic zone contact model were introduced to determine the optimum local failure model. Plastic collapse tests and finite element analyses using thin plates with two collinear through-wall cracks were performed for the selection of the optimum local failure model. By comparing the test results with the prediction results obtained from local failure models, the reaction force model and plastic zone contact model were determined as the optimum local failure models.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2005.05.024</doi><tpages>10</tpages></addata></record> |
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subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Installations for energy generation and conversion: thermal and electrical energy Nuclear fuels |
title | Optimum local failure model of steam generator tubes with multiple axial through-wall cracks |
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