Abstract
The results of a low-pressure subcooled flow boiling experiment simulated with the RELAP5/MOD3.2 thermal-hydraulic computer program are presented. The objective of the present study is to assess the suitability of application of the RELAP5 computer program for the thermal hydraulic safety analysis of research reactors. These reactors as the High Flux Australian reactor HIFAR operate at near-atmospheric pressures with upward forced convective flow. Subcooled boiling phenomenon plays an important role in the heat transfer aspects of this reactor. It is found that the void fraction profile predicted by the code for the various experimental conditions differ considerably from the experimental results.
Volume Subject Area:
CFD and Thermal Hydraulics Analysis in Nuclear Reactors
Topics:
Boiling,
Computers,
Simulation,
Subcooling,
Computer software,
Flow (Dynamics),
Heat transfer,
Porosity,
Pressure,
Safety
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Copyright © 1998 by The American Society of Mechanical Engineers
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