Published 1985
| Version v1
Book
Mean flow measurements in rod bundle subchannels
Creators
- 1. Univ. of Ottawa, Dept. of Mechanical Engineering, Ottawa, Ontario (Canada)
Description
This paper reports the detailed mapping of coolant flow and heat transfer characteristics within a 37-rod fuel bundle of the CANDU nuclear reactor. During the initial phase, the study covers isothermal, single-phase, water flow through a double-scale model of the bundle, placed in a specially designed, closed circuit, water tunnel. The mass flux rate and the Reynolds number during the tests were comparable to those in the reactor core
Additional details
Publishing Information
- Publisher
- Univ. of Western Ontario
- Imprint Place
- London, Ontario (Canada)
- ISBN
- 0-920049-01-X
- Imprint Title
- Tenth Canadian Congress of applied mechanics : CANCAM'85. Proceedings
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.2) p. B197-B198
Conference
- Title
- CANCAM'85
- Acronym
- 10. Canadian Congress of applied mechanics
- Dates
- 2-7 Jun 1985
- Place
- London, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 37113291
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COOLANT LOOPS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; REYNOLDS NUMBER; WATER
- Descriptors DEC
- COOLING SYSTEMS; DIMENSIONLESS NUMBERS; ENERGY SYSTEMS; ENERGY TRANSFER; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 1 ref., 6 figs.