Predictions of rewetting process for a nuclear fuel rod using first-principles equations

Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review

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Author(s)

  • Y. M. Ferng
  • C. C. Chieng
  • C. Pan

Detail(s)

Original languageEnglish
Pages (from-to)189-205
Journal / PublicationNuclear Engineering and Design
Volume126
Issue number2
Publication statusPublished - 2 Apr 1991
Externally publishedYes

Abstract

The rewetting of a nuclear fuel rod is investigated numerically by a conjugated heat transfer model using first-principles equations. The two-phase flow in the coolant channel is treated by a turbulent, locally-homogenized model. The heat transfer coefficient, rewetting temperature and rewetting velocity are parts of the solution. The critical heat flux predicted by the model agrees with the experimental data available in other literature to a reasonable extent. The effect of gap resistance on the rewetting process is studied and the results show agreement with earlier analytical models. The predicted rewetting velocity agrees with experimental data within 15% discrepancy. © 1991.

Citation Format(s)

Predictions of rewetting process for a nuclear fuel rod using first-principles equations. / Ferng, Y. M.; Chieng, C. C.; Pan, C.
In: Nuclear Engineering and Design, Vol. 126, No. 2, 02.04.1991, p. 189-205.

Research output: Journal Publications and Reviews (RGC: 21, 22, 62)21_Publication in refereed journalpeer-review