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Morris, D.G.; Mullins, C.B.; Yoder, G.L.
Oak Ridge National Lab., TN (USA)1983
Oak Ridge National Lab., TN (USA)1983
AbstractAbstract
[en] The effects of thermodynamic nonequilibrium in dispersed flow film boiling heat transfer are examined. Steady-state and transient rod-bundle data are used to evaluate several empirical heat-transfer models commonly employed to predict post-CHF behavior. The models that account for thermodynamic nonequilibrium perform adequately, while those that ignore nonequilibrium effects incur errors in wall superheat as high as 1900K. Nonequilibrium effects can also be treated by explicitly modeling the phenomena. The thermal-hydraulic code COBRA-TF employs this approach. Using bundle data, the models in the code are evaluated. Analysis suggests that the interfacial heat transfer is overpredicted
Original Title
PWR; BWR
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Source
1983; 10 p; 2. international topical meeting on nuclear reactor thermal hydraulics; Santa Barbara, CA (USA); 11 - 13 Jan 1983; Available from NTIS MF A01; 2 as DE83006143
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Report
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Conference
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