Published May 2000
| Version v1
Journal article
One-Dimensional void fraction distribution of gas-liquid two-phase flow in a rod bundle
- 1. Kobe Univ. (Japan). Dept. of Mech. Eng.
Description
Visualization and void fraction measurement are important to study the behaviors of a two-phase flow. It is often difficult to visualize two-phase flows and to measure void fraction distributions in complicated conduits like a rod bundle. In this study, visualization of two-phase flow in a rod bundle near the spacer were carried out and the void fraction distributions were measured by using neutron radiography system in Japan Atomic Energy Research Institute. Quantitative void fraction distributions in a rod bundle were presented. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Dennetsu Shinpojiumu Koen Ronbunshu
- Journal Volume
- 37
- Journal Issue
- 2
- Journal Page Range
- p. 473-474
- CODEN
- NDSRD4
Conference
- Title
- 37. national heat transfer symposium of Japan
- Dates
- 29-31 May 2000
- Place
- Kobe (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31057781
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUBBLE GROWTH; FLOW VISUALIZATION; FUEL ELEMENT CLUSTERS; NEUTRON ABSORBERS; NEUTRON RADIOGRAPHY; REACTOR COOLING SYSTEMS; SPACERS; SPATIAL DISTRIBUTION; TWO-PHASE FLOW; VOID FRACTION; WATER COOLED REACTORS
- Descriptors DEC
- COOLING SYSTEMS; DISTRIBUTION; ENERGY SYSTEMS; FLUID FLOW; FUEL ASSEMBLIES; INDUSTRIAL RADIOGRAPHY; MATERIALS TESTING; NONDESTRUCTIVE TESTING; REACTOR COMPONENTS; REACTORS; TESTING
Optional Information
- Notes
- 6 figs.