Published 1992
| Version v1
Book
Convective heat transfer in spent fuel canisters
Creators
- 1. Tennessee Univ., Knoxville, TN (United States). Dept. of Mechanical and Aerospace Engineering
- 2. College of Engineering, Colorado State Univ., Fort Collins, CO (United States)
Description
In this paper engineering correlations for convective heat transfer in enclosed vertical rod-bundles are reviewed. A criterion is proposed for determination of the heat transfer regime in the enclosure so that relevant correlations can be used. Moreover, a procedure for calculation of an approximate maximum center rod temperature in the canister is proposed. The procedure is applied to a PWR assembly, and the predicted values are compared with the measured data. Considering the approximate nature of the proposed procedure and the complexity of the problem, the predicted values are judged to be in good agreement with the measured values
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 0-87262-891-4
- Imprint Title
- Proceedings of high level radioactive waste management
- Imprint Pagination
- 2425 p.
- Journal Page Range
- p. 773-778.
Conference
- Title
- 3. international high level radioactive waste management (IHLRWM) conference.
- Dates
- 12-16 Apr 1992.
- Place
- Las Vegas, NV (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24015558
- Subject category
- S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINERS; CONVECTION; CORRECTIONS; ENGINEERING; FUEL ASSEMBLIES; FUEL ELEMENT CLUSTERS; PWR TYPE REACTORS; REVIEWS; SPENT FUELS
- Descriptors DEC
- DOCUMENT TYPES; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUELS; HEAT TRANSFER; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-920430--.