Simulation of Boiling Flow Experiments Close to CHF with the Neptune_CFD Code
Author(s) -
Boštjan Končar,
Borut Mavko
Publication year - 2008
Publication title -
science and technology of nuclear installations
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.417
H-Index - 24
eISSN - 1687-6083
pISSN - 1687-6075
DOI - 10.1155/2008/732158
Subject(s) - subcooling , computational fluid dynamics , mechanics , boiling , materials science , flow (mathematics) , heat flux , thermodynamics , flow boiling , critical heat flux , heat transfer , physics
A three-dimensional two-fluid code Neptune_CFD has been validated against the Arizona State University (ASU) and DEBORA boiling flow experiments. Two-phase flow processes in the subcooled flow boiling regime have been studied on ASU experiments. Within this scope a new wall function has been implemented in the Neptune_CFD code aiming to improve the prediction of flow parameters in the near-wall region. The capability of the code to predict the boiling flow regime close to critical heat flux (CHF) conditions has been verified on selected DEBORA experiments. To predict the onset of CHF regime, a simplified model based on the near-wall values of gas volume fraction was used. The results have shown that the code is able to predict the wall temperature increase and the sharp void fraction peak near the heated wall, which are characteristic phenomena for CHF conditions
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