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Jeong, Jae-Uk; Yu, Seung-Cheon; Chang, Yoon-Suk; Kim, Young-Jin; Hwang, Seong-Sik; Kim, Hong-Pyo
Proceedings of the KNS spring meeting2008
Proceedings of the KNS spring meeting2008
AbstractAbstract
[en] Steam generator (SG) tubes are one of pressure boundary components, which perform the role of heat transportation from primary system toward secondary system in a nuclear power plant. In general, a SG consists of thousands thin tubes with 10mm radius and 1mm thickness, approximately. Since it was reported that SG tubes in pressurized water reactors have experienced diverse types of degradation, to prevent rupture of them caused by unanticipated scenarios, lots of structural integrity evaluation and leak rate estimation models were proposed. Despite the efficiency of these methods, their application is not easy on the field because of complicated calculation schemes required. The purpose of the present paper is to introduce an activity to develop a program which is applicable to perform structural integrity assessment of SG tubes with various flaw types, rapidly and accurately, by employing promising models
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Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; May 2008; [2 p.]; 2008 spring meeting of the KNS; Kyeongju (Korea, Republic of); 29-30 May 2008; Available from KNS, Daejeon (KR); 7 refs, 5 figs
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Miscellaneous
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Conference
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