Effects of various correlations on the COBRA-IIIC Code predictions and the critical heat flux
Creators
- 1. Heat Transfer Research Facility Columbia University, New York, NY
Description
A study was conducted to investigate the sensitivity of the local conditions predicted by the COBRA-IIIC code and thus the predicted critical heat flux (CHF) to a range of widely used correlations for subcooled void fraction, bulk void fraction, two-phase friction multiplier and turbulent mixing parameter. The sensitivity study was performed with sixty three CHF data points from a 21 rod bundle electrically simulating a pressurized water reactor (PWR). The data cover the parameter ranges of pressure from 6.88 to 15.48 MPa and mass flux from 680 to 4080 Kg/(m2.s). The results of the sensitivity analysis show that the COBRA-IIIC predictions are not very sensitive to either the subcooled void correlations or the bulk void correlations and are moderately dependent on the two-phase friction multiplier correlations. The turbulent mixing parameters investigated have the most marked effect on the COBRA-IIIC predictions
Additional details
Publishing Information
- Journal Title
- Am. Soc. Mech. Eng., [Pap.]
- Journal Volume
- 83-HT-108
- Series
- Am. Soc. Mech. Eng., [Pap.].
- Journal Page Range
- 8
- ISSN
- 0402-1215
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15061943
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- C CODES; COMPUTER CODES; COMPUTERIZED SIMULATION; CORRELATIONS; CRITICAL HEAT FLUX; FORECASTING; FUEL ELEMENT CLUSTERS; PWR TYPE REACTORS; REACTOR SIMULATORS; SENSITIVITY; VOID FRACTION
- Descriptors DEC
- ANALOG SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUNCTIONAL MODELS; HEAT FLUX; POWER REACTORS; REACTORS; SIMULATION; SIMULATORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS