Published September 2015
| Version v1
Journal article
Analysis of subcooled boiling in PWR rod bundle channel
- 1. State Key Laboratory of Multiphase Flow in Power Engineering, Xi'n Jiaotong University, Xi'an (China)
- 2. Shanghai Nuclear Engineering Research and Design Institute, Shanghai (China)
Description
The RPI (Rensselaer Polytechnic Institute) wall boiling model, embedded in the context of two-fluid model of Fluent14.5, was applied to simulate subcooled boiling in core fuel bundle channel with mixing vanes and space grid. The subcooled boiling key parameters including flow field, temperature field and void fraction distribution were obtained. The analysis of the effect of mixing vanes and space grid on flow channel thermal-hydraulic characteristics was conducted. It is shown that the existence of space grid can cause a large pressure drop, and mixing vanes have a great influence on the key parameters of flow field and temperature field. The results of RPI model show a good agreement with Bartolemei experiment data. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 49
- Journal Issue
- 9
- Journal Page Range
- p. 1579-1585
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 51018357
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; DISTRIBUTION; FUEL ELEMENT CLUSTERS; FUEL RODS; NUMERICAL ANALYSIS; PRESSURE DROP; PWR TYPE REACTORS; REACTOR CORES; SPACERS; SUBCOOLED BOILING; THERMAL HYDRAULICS; VOID FRACTION
- Descriptors DEC
- BOILING; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL ELEMENTS; HYDRAULICS; MATHEMATICS; MECHANICS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 figs., 2 tabs., 10 refs.; http://dx.doi.org/10.7538/yzk.2015.49.09.1579