Analysis of two-phase flow inter-subchannel mass and momentum exchanges by the two-fluid model approach
Creators
- 1. Tokyo Institute of Technology (Japan)
- 2. ENO Mathematical Analysis, Tokyo (Japan)
- 3. Kumamoto Univ., Kumamoto (Japan)
Description
A new void drift model for the subchannel analysis method is presented for the thermohydraulics calculation of two-phase flows in rod bundles where the flow model uses a two-fluid formulation for the conservation of mass, momentum and energy. A void drift model is constructed based on the experimental data obtained in a geometrically simple inter-connected two circular channel test sections using air-water as working fluids. The void drift force is assumed to be an origin of void drift velocity components of the two-phase cross-flow in a gap area between two adjacent rods and to overcome the momentum exchanges at the phase interface and wall-fluid interface. This void drift force is implemented in the cross flow momentum equations. Computational results have been successfully compared to experimental data available including 3x3 rod bundle data
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Sessions 17-24
- Imprint Pagination
- 825 p.
- Journal Page Range
- p. 2721-2737.
- Report number
- NUREG/CP--0142-Vol.4
Conference
- Title
- 7. international meeting on nuclear reactor thermal hydraulics.
- Dates
- 10-15 Sep 1995.
- Place
- Saratoga, NY (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27019715
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MATHEMATICAL MODELS; TWO-PHASE FLOW
- Descriptors DEC
- ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-950904--Vol.4.