Published November 30, 1994 | Version v1
Journal article

Void fraction along a vertical heated rod bundle under flow stagnation conditions

  • 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