Steady-state film-boiling data in rod-bundle geometry and non-equilibrium correlation assessment
A series of 22 steady-state, rod bundle, dispersed flow film boiling experiments has been performed in the Thermal-Hydraulic Test Facility (THTF), a pressurized-water loop containing 64 full-length electrically heated rods. Test parameters in the upflow experiments cover a wide range of conditions typical of those which might be encountered during a nuclear reactor loss-of-coolant accident. Local equilibrium fluid conditions were calculated using mass and energy conservation considerations. Experimentally determined heat transfer coefficients were compared to several available film boiling heat transfer correlations: Dougall-Rohsenow, Groeneveld 5.7, Groeneveld-Delorme, Chen, Jones-Zuber, and Yoder-Rohsenow. The Groeneveld 5.7 correlation tended to predict the data better than any other correlation tested. The Dougall-Rohsenow correlation tends to overpredict the data while the Yoder-Rohsenow correlation predicted the data better than the other nonequilibrium correlations examined. However, all of the nonequilibrium correlations generally underpredict the heat transfer.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5338929
- Report Number(s):
- CONF-820604-9; ON: DE82017479; TRN: 82-015958
- Resource Relation:
- Conference: AIAA/ASME joint conference on fluids, plasma, thermophysics and heat transfer, St Louis, MO, USA, 7 Jun 1982; Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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LOSS OF COOLANT
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COOLANT LOOPS
CORRELATIONS
EXPERIMENTAL DATA
HEAT TRANSFER
RESISTANCE HEATING
SIMULATION
STEADY-STATE CONDITIONS
ACCIDENTS
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