Published May 1993
| Version v1
Journal article
In-bundle void measurement of a BWR fuel assembly by X-ray CT scanner
- 1. Toshiba Corp., Kawasaki, Kanagawa (Japan)
Description
The purpose of this study is to measure the local void distribution in the full scale BWR fuel assembly by using the X-ray CT scanner and to discuss the rod bundle void data. Major conclusions obtained are as follows; (1) Local void fraction data in the 8x8 rod bundle have been obtained. (2) The cross-sectional averaged void fraction for a 8x8 rod bundle can be correlated by the Drift-Flux model and the value of Co and VGj can be obtained by the present data. (3) The EPRI void correlation can be predicted the present void data very well. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Dennetsu Shinpojiumu Koen Ronbunshu
- Journal Volume
- 30
- Journal Issue
- 1
- Journal Page Range
- p. 118-120.
- CODEN
- NDSRD4
Conference
- Title
- 30. national heat transfer symposium of Japan.
- Dates
- 26-28 May 1993.
- Place
- Yokohama (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 26008502
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CAT SCANNING; FUEL ASSEMBLIES; FUEL ELEMENT CLUSTERS; HYDRAULICS; POWER DISTRIBUTION; REACTOR CORES; TWO-PHASE FLOW; VISIBILITY; VOID FRACTION; WATER VAPOR
- Descriptors DEC
- COMPUTERIZED TOMOGRAPHY; DISTRIBUTION; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUIDS; GASES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; TOMOGRAPHY; VAPORS; WATER COOLED REACTORS; WATER MODERATED REACTORS