Published November 30, 1994
| Version v1
Journal article
Void fraction along a vertical heated rod bundle under flow stagnation conditions
Creators
- 1. Centro Atomico Bariloche and Instituto Balseiro, 8400 Bariloche (Argentina)
Description
Axial void fraction distributions were measured in a vertical cylindrical channel with a four-rod heated bundle under flow stagnation conditions. The development length for the void fraction profile was measured. It was observed that the void fraction profile does not always increase progressively along the channel, but peaks where most of the coalescence takes place. The ability of currently used drift-flux correlations to predict such behavior is questioned by the present experimental results. ((orig.))
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 152
- Journal Issue
- 1-3
- Journal Page Range
- p. 225-230.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 26044843
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- DENSIMETERS; FUEL ELEMENT CLUSTERS; LOSS OF COOLANT; RADIOMETRIC GAGES; REACTOR SAFETY EXPERIMENTS; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; FLUID FLOW; FUEL ASSEMBLIES; MEASURING INSTRUMENTS; REACTOR ACCIDENTS