Validation of COMMIX with Westinghouse AP-600 PCCS test data [electronic resource].
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1993.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 27 pages : digital, PDF file
- Additional Creators:
- Argonne National Laboratory
U.S. Nuclear Regulatory Commission
United States. Department of Energy. Office of Scientific and Technical Information
- Small-scale test data for the Westinghouse AP-600 Passive Containment Cooling System (PCCS) have been used to validate the COMMIX computer code. To evaluate the performance of the PCCS, two transient liquid-film tracking models have been developed and implemented in the CO code. A set of heat transfer models and a mass transfer model based on heat and mass transfer analogy were used for the analysis of the AP-600 PCCS. It was found that the flow of the air stream in the annulus is a highly turbulent forced convection and that the flow of the air/steam mixture in the containment vessel is a mixed convection. Accordingly, a turbulent-forced-convection heat transfer model is used on the outside of the steel containment vessel wall and a mixed-convection heat transfer model is used on the inside of the steel containment vessel wall. The results from the CO calculations are compared with the experimental data from Westinghouse PCCS small-scale tests for average wall heat flux, evaporation rate, containment vessel pressure, and vessel wall temperature and heat flux distributions; agreement is good. The CO calculations also provide detailed distributions of velocity, temperature, and steam and air concentrations.
- Published through SciTech Connect.
21. water reactor safety information meeting,Bethesda, MD (United States),25-27 Oct 1993.
Sha, W.T.; Sun, J.G.; Ding, J.; Chien, T.H.
- Funding Information:
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