Published July 2003
| Version v1
Journal article
Flow visualization on gas-liquid two-phase flows in a parallel helical coil tube
Creators
- 1. Tokyo Univ., Tokyo (Japan)
- 2. Hokkaido Univ., Sapporo, Hokkaido (Japan)
- 3. Fukui Univ., Fukui (Japan)
- 4. Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)
Description
In the steam generator of the fast breeder prototype reactor 'Monju', heat exchange tubes of helical coil type are utilized. Steam-water two-phase flows in the helical coil tube have unique characteristic due to effects of centrifugal acceleration. In this paper, we visualized gas-liquid two-phase flows in each the helical coil tubes with two curvature radii to investigate the effect of centrifugal acceleration, and also the slug flow in parallel helical coil tubes with same pressure condition at outlet part are visualized. (author)
Additional details
Publishing Information
- Journal Title
- Kashika Joho
- Journal Volume
- 23
- Journal Issue
- suppl.1
- Journal Page Range
- p. 373-376
- ISSN
- 0916-4731
Conference
- Title
- 31. symposium on visualization
- Dates
- 22-24 Jul 2003
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 34076885
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLOW VISUALIZATION; HEAT EXCHANGERS; HELICAL CONFIGURATION; MONJU REACTOR; PHASE SHIFT; PRESSURE GRADIENTS; TUBES; TWO-PHASE FLOW
- Descriptors DEC
- BREEDER REACTORS; CONFIGURATION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Notes
- 1 ref., 6 figs., 2 tabs.