Evaluation of predictability of multiple CHF events
Description
The phenomenon of multiple CHF events in rod bundle heat transfer tests, referring to the occurrence of CHF on more than one rod or at more than one location on one rod is examined. The adequacy CE-1, BandW-2, and Columbia subchannel CHF correlations in predicting higher order CHF events is ascertained based on local coolant conditions obtained with the COBRA IIIC sub channel code. The data from three sets of tests simulating both PWR and BWR reactor cores obtained at the Heat Transfer Research Facility of Columbia University are studied using a combination of statistical analyses and parametric studies. Results show that: 1) the characteristic behavior of the higher rank CHF are essentially the same as those of the first CHF; and 2) the presently available subchannel CHF correlations predict the CHF events of higher rank with the same degree of accuracy as the first CHF
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-89448-110-X
- Imprint Title
- Thermal hydraulics of nuclear reactors
- Journal Page Range
- p. 390-397.
Conference
- Title
- 2. international topical meeting on nuclear reactor thermal hydraulics (ANS).
- Dates
- 11-13 Jan 1983.
- Place
- Santa Barbara, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17089430
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BWR TYPE REACTORS; C CODES; COOLANTS; CORRELATIONS; CRITICAL HEAT FLUX; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; MULTI-PARAMETER ANALYSIS; PWR TYPE REACTORS; REACTOR CORES; RESEARCH PROGRAMS; STATISTICS; TESTING
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAT FLUX; MATHEMATICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS