Published October 1998
| Version v1
Journal article
Analyses of subcooled CCFL tests for evaluation of WCOBRA/TRAC applicability
Creators
- 1. Westinghouse Electric Corp., Pittsburgh, PA (United States). Nuclear Service Div.
Description
The WCOBRA/TRAC-MOD7A, Rev. 1 code is currently licensed for best estimate large break LOCA analyses of 3 and 4 loop PWRs with emergency core cooling system injection located in the cold legs. As a part of the licensing effort to extend the code applicability to an upper plenum injection plant, the codes ability to predict subcooled flooding on a perforated plate was assessed by analyses of GE counter current flow limit tests and by comparison to the Bankoff flooding correlation (Bankoff et al. (1981)). The observed code model bias for subcooled CCFL can be eliminated by applying multiplication factors to the interfacial condensation and the interfacial drag models. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 185
- Journal Issue
- 2-3
- Journal Page Range
- p. 127-140
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 30003125
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AIR; BUBBLES; COOLANT LOOPS; COUNTER CURRENT; FLOW MODELS; LOSS OF COOLANT; PWR TYPE REACTORS; STEAM; STEAM INJECTION; SUBCOOLING; TEST FACILITIES; TWO-PHASE FLOW; W CODES; WATER
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID INJECTION; FLUIDS; GASES; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WELL STIMULATION
Optional Information
- Notes
- 9 refs.