The technique of calculation of non-equilibrium two-phase flows in pin bundles using quasi-two-dimensional approaches and subchannel approximation
- 1. Inst. of Physics and Power Engineering, Obninsk (USSR)
Description
In this paper a theoretical approach to heat bundle parameter calculation in boiling reactors which resulted in the use of the subchannel approximation procedure with the verified system of equations for the subchannels is described. The system of equations is written for the drift flux model of the two-phase non-equilibrium flow in the quasi-two-dimensional approximation. Recommendations for calculating the distribution parameters included in the quasi-two-dimensional problem formulation are given. Combining the subchannel approximation with the quasi-two-dimensional approach helps to keep up acceptable calculation precision for the bundles with relatively large subchannels when the cross-sectional phase parameter distribution for each subchannel must be taken into consideration. Some calculation results are presented
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0546-8
- Imprint Title
- Advances in gas-liquid flows 1990
- Imprint Pagination
- 490 p.
- Journal Page Range
- p. 321-330.
Conference
- Title
- American Society of Mechanical Engineers (ASME) winter annual meeting.
- Dates
- 25-30 Nov 1990.
- Place
- Dallas, TX (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23067225
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CALCULATION METHODS; FLUID MECHANICS; FUEL CHANNELS; HEAT FLUX; PHASE STUDIES; TWO-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID FLOW; MECHANICS; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901194--.