Published August 1975
| Version v1
Journal article
Nuclear-thermal-hydraulic characteristics of BWR fuel bundles
- 1. Hitachi Ltd., Kawasaki, Kanagawa (Japan). Atomic Energy Research Lab.
Description
no abstract available
Additional details
Identifiers
- DOI
- 10.3327/jnst.12.526;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology
- Journal Volume
- 12
- Journal Issue
- 8
- Series
- J. Nucl. Sci. Technol. (Tokyo).
- Journal Page Range
- 526-528
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 7269063
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- No Abstract
- Descriptors DEI
- BWR TYPE REACTORS; CONTROL ROD WORTHS; DIFFUSION; FUEL ELEMENT CLUSTERS; HYDRAULICS; POWER DENSITY; PROGRAMMING; SPATIAL DISTRIBUTION; SUBCOOLED BOILING; THERMAL ANALYSIS; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- BOILING; DISTRIBUTION; FLUID FLOW; FUEL ASSEMBLIES; PHASE TRANSFORMATIONS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Published in summary form only.; Updated automatically by Metadata and Full-Text Enrichment Agent