The paper presents validation results for multichannel vessel thermal-hydraulic models in CATHARE used in coupled 3D neutronic/thermal hydraulic calculations. The mixing is modeled with cross flows governed by local pressure drops. The test cases are from the OECD VVER-1000 coolant transient benchmark (V1000CT) and include asymmetric vessel flow transients and main steam line break (MSLB) transients. Plant data from flow mixing experiments are available for comparison. Sufficient mesh refinement with up to 24 sectors in the vessel is considered for acceptable resolution. The results demonstrate the applicability of such validated thermal-hydraulic models to MSLB scenarios involving thermal mixing, azimuthal flow rotation, and primary pump trip. An acceptable trade-off between accuracy and computational efficiency can be obtained. © 2010 I. Spasov et al.
CITATION STYLE
Kolev, N. P., Spasov, I., Donov, J., & Sabotinov, L. (2010). CATHARE multi-1D modeling of coolant mixing in VVER-1000 for RIA analysis. Science and Technology of Nuclear Installations, 2010. https://doi.org/10.1155/2010/457094
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