Investigation of two-phase flow characteristics in the BWR steam separator -- Air-water experiment and 3D two-fluid model analysis
- 1. Toshiba Corp., Yokohama, Kanagawa (Japan). Nuclear Energy Group
- 2. Toshiba Corp., Kawasaki, Kanagawa (Japan). Nuclear Energy Group
Description
Two-phase flow with swirl motion in the BWR steam separators was examined both experimentally and analytically. Experimentally, one third (1/3) scale model of the current ABWR steam separator was tested din the atmospheric air-water test loop. Using the test section made of transparent plastic to facilitate understanding of flow patterns, the complex two-phase flow behaviors at various locations of the current BWR steam separator were visualized. Qualitatively, using the air-water test loop, geometrical effects of the current BWR steam separator on carryover rate were examined. In parallel, a computer code based on two-fluid model formulation in axially symmetrical 3-D space was developed. After comparisons of the code predictions with both the air-water and the steam-water carryover test results, it is found that both air-water system and steam-water system can be analyzed successfully by the single two-fluid model and that the two-fluid analysis can be used in both design work and performance analysis of steam separators
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1226-X
- Imprint Title
- ICONE-4: Proceedings. Volume 1 -- Part A: Basic technological advances
- Imprint Pagination
- 534 p.
- Journal Page Range
- p. 131-139.
Conference
- Title
- ASME/JSME international conference on nuclear engineering.
- Acronym
- ICONE 4
- Dates
- 10-13 Mar 1996.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27054024
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; FLOW MODELS; PARALLEL PROCESSING; SCALE MODELS; STEAM SEPARATORS; THEORETICAL DATA; TWO-PHASE FLOW; VORTEX FLOW
- Descriptors DEC
- DATA; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; INFORMATION; MATHEMATICAL MODELS; NUMERICAL DATA; POWER REACTORS; PROGRAMMING; REACTORS; SEPARATION EQUIPMENT; SIMULATION; STRUCTURAL MODELS; THERMAL REACTORS; VAPOR SEPARATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-960306--.