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Park, S. K.; Kim, H. D.; Lee, S. J.; Shin, D. M.; Cho, N. C.
Proceedings of the KNS spring meeting2008
Proceedings of the KNS spring meeting2008
AbstractAbstract
[en] A significant number of pressurized water reactor (PWR) plants have reported decreases in their steam generator steam pressure during the last several years. Because a steam pressure decrease causes a reduction of the electrical power generating capacity directly, a steam generator's thermal performance is one of the important issues for steam generator maintenance. Therefore, the Korea Hydro and Nuclear Power Company has established an on-line acquisition system for plant operational parameters as a part of the Steam Generator Management Program (SGMP). Recently, plant-specific tools for calculating the overall heat transfer coefficient and the global fouling factor were also constructed and applied to some plants
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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); 3 refs, 3 figs
Record Type
Miscellaneous
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Conference
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