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Park, I. K.; Cho, H. K.; Kim, J.; Yoon, H. Y.; Jeong, J. J.
Proceedings of the KNS spring meeting2008
Proceedings of the KNS spring meeting2008
AbstractAbstract
[en] A component-scale thermal-hydraulics analysis module, CUPID has been being developed for a transient three-dimensional two-phase flow analysis of nuclear reactor components. CUPID is based on a two-fluid, three-field model, which is solved by using an unstructured finite volume method. The three fields in the CUPID code represent a continuous liquid, an entrained liquid, and a vapor field. At present the two liquid fields in the CUPID code are assumed to be in a thermally equilibrium state. In this paper, non-equilibrium energy equations for droplets and continuous liquid fields were implemented and assessed. In addition, the shared memory parallelism for the CUPID code was tested using a quad-core CPU personal computer
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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); 4 refs, 3 figs, 1 tab
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Miscellaneous
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Conference
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