Considerations for comparing CHF correlations
Creators
- 1. Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Fuel Div.
Description
Accuracy is a key consideration when selecting a critical heat flux (CHF) correlation for use in DNB safety analyses of pressurized water reactors (PWR). The desire is to minimize the amount of power margin which must be set aside to cover the uncertainty of the correlation. The accuracy of a CHF correlation for a particular fuel design may be determined by evaluating its ability to predict DNB conditions in tests performed with rod bundle geometries which simulate the production fuel assemblies. The results of such evaluations are typically tabulated in terms of the average measured-to-predicted (or predicted-to-measured) critical heat flux ratio (CHFR) or critical power ratio (CPR) for the data, and the corresponding sample standard deviation. PWR fuel vendors have historically chosen to express the accuracy of their correlations using CHFR statistics. This is a logical choice, since DNB safety analysis are performed using critical heat flux ratios. Recently a number of investigators have attempted to compare the accuracies of different correlations for predicting publicly available DNB test data. In a few cases a comparison of CHFR statistics was used to rank the various correlations. It will be shown in this paper that such an approach can be misleading, and will not always lead to the selection of the most accurate correlation. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Soc. of Japan.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of second international topical meeting on nuclear power plant thermal hydraulics and operations
- Imprint Pagination
- 1191 p.
- Journal Page Range
- p. 1/9-1/13.
Conference
- Title
- 2. international topical meeting on nuclear power plant thermal hydraulics and operations.
- Dates
- 15-17 Apr 1986.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18061292
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORRELATIONS; CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; FUEL ELEMENT CLUSTERS; FUEL RODS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS
- Descriptors DEC
- BOILING; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAT FLUX; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS