Published 1987
| Version v1
Book
An assessment of eight void fraction models
Creators
- 1. Electric Power Research Institute, 3412 Hillview Avenue, P.O. Box 10412, Palo Alto, CA (USA)
Description
This paper provides an assessment of eight well-known models for predicting void fraction. The void fraction predictions from void models were compared using steady-state steam-water test data for vertical configurations that included almost 1500 data points representing several areas of interest to nuclear analysts such as (1) high pressure-high flows, (2) high pressure-low flows, (3) low pressure-low flow, (4) countercurrent flooding limitation, (5) natural circulation flows, and (6) co-current downflows. The data was representative of PWR and BWR fuel assemblies and pipes up to 18 inches in diameter
Additional details
Publishing Information
- Publisher
- American Institute of Chemical Engineers.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Heat transfer: Pittsburgh 1987
- Journal Page Range
- p. 249-254.
Conference
- Title
- 24. national heat transfer conference and exhibition.
- Dates
- 9-12 Aug 1987.
- Place
- Pittsburgh, PA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19084499
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPRESSIBLE FLOW; FLOW MODELS; FUEL ASSEMBLIES; GAS FLOW; LIQUID FLOW; PIPES; PWR TYPE REACTORS; STEADY-STATE CONDITIONS; STEAM; TWO-PHASE FLOW; VOID FRACTION; WATER
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID FLOW; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTORS; SOLVENTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS