Published 1997 | Version v1
Journal article Metadata-only

Measurements of the void-fraction distribution in a simulated fuel assembly and the role of the void-fraction on the dynamics of a natural circulation loop

Creators

  • 1. Delft University of Technology (Netherlands). Interfaculty Research Institute
  • 2. Delft University of Technology (Netherlands). Kramers Laboratorium voor Fysische Technologie

Description

The role of the void-fraction in a natural circulation BWR has been investigated using the scaled natural circulation loop facility DESIRE. To this end, measurements of the void-fraction have been performed on a subchannel basis using gamma-transmission tomography. Subcooled boiling and void slip were observed. Lateral transport of void between the subchannels was negligible. Also the effect of the void-fraction on natural circulation has been studied both in steady-state and dynamic situations using noise analysis techniques. Results of the steady-state and dynamic measurements are compared. The void-to-flow transfer function is strongly affected by transport of void from the core region to the riser section. (author)

Additional details

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
24
Journal Issue
16
Journal Page Range
p. 1333-1347.
ISSN
0306-4549
CODEN
ANENDJ

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
28061927
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
BWR TYPE REACTORS; CIRCULATING SYSTEMS; COOLANT LOOPS; EXPERIMENTAL DATA; NATURAL CONVECTION; TEST FACILITIES; VOID FRACTION
Descriptors DEC
CONVECTION; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS