An improved theoretical critical heat flux model for low-quality flow
Creators
- 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
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21059344
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CRITICAL HEAT FLUX; EXPERIMENTAL DATA; FUEL ELEMENT CLUSTERS; PWR TYPE REACTORS; SUBCOOLED BOILING
- Descriptors DEC
- BOILING; DATA; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAT FLUX; INFORMATION; NUMERICAL DATA; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS