Published December 1989 | Version v1
Journal article

An improved theoretical critical heat flux model for low-quality flow

  • 1. National Tsing Hua Univ., Hsinchu (Taiwan). Dept. of Nuclear Engineering
  • 2. Institute of Nuclear Energy Research, Lung-Tan (Taiwan)

Description

Based on the Helmholtz instability at the microlayer/vapor interface as a trigger condition for microlayer dryout, a previous study developed a mechanistic critical heat flux (CHF) model for subcooled flow boiling. An improved CHF model is implemented with more solid theoretical bases for subcooled and low-quality flow boiling under pressurized water reactor conditions. Comparisons between the predictions and experimental data show that the present model is more accurate than the well-known theoretical CHF model and empirical CHF correlations for water flowing through uniformly heated round tubes within the applicable ranges. The applicability of the present model to rod bundles is also under investigation. High satisfactory results are obtained from the comparisons of predicted to observed bundle critical power

Additional details

Publishing Information

Journal Title
Nuclear Technology
Journal Volume
88
Journal Issue
3
Series
Nucl. Technol.
Journal Page Range
291-306
ISSN
0029-5450
CODEN
NUTYB

INIS