Integral boundary layer heat transfer modeling for Tehran Research Reactor
Creators
- 1. Engineering Science Research Group, Nuclear Science Research School, Nuclear Science and Technology Research Institute, AEOI, P.O. Box 11365 3486, Tehran (Iran, Islamic Republic of)
Description
In the present work the validity of applying the Boussinesq approximation in the analysis of natural convection heat transfer along nuclear fuel plates with large coolant channel aspect ratios is evaluated. The Boussinesq approximation is introduced into the integral boundary layer equations governing the system to describe the velocity and temperature distributions of the coolant in the cooling channels. The fuel plate temperature is related to the adjacent coolant fluid temperature by a fundamental law in conduction heat transfer. Air and water are considered as fluids. The coolant flow is assumed to be fully developed which is a convenient assumption for coolant channels having large aspect ratios. Obtained results indicate that the Boussinesq approximation is merely applicable over a limited range of coolant channel outlet fluid temperatures. The use of this approximation produces conservative estimation of the critical plate power for air flow and non-conservative estimation of the critical plate power for water flow.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2010.10.001Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2010.10.001;
- PII
- S0149197010001563;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 53
- Journal Issue
- 2
- Journal Page Range
- p. 223-228
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51010779
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- AIR FLOW; APPROXIMATIONS; ASPECT RATIO; BOUNDARY LAYERS; COMPUTERIZED SIMULATION; COOLANT LOOPS; COOLANTS; FUEL PLATES; NATURAL CONVECTION; TEMPERATURE DISTRIBUTION; UTRR REACTOR; WATER
- Descriptors DEC
- CALCULATION METHODS; CONVECTION; COOLING SYSTEMS; DIMENSIONLESS NUMBERS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ELEMENTS; GAS FLOW; HEAT TRANSFER; HYDROGEN COMPOUNDS; LAYERS; MASS TRANSFER; OXYGEN COMPOUNDS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Copyright © 2010 Elsevier Ltd. All rights reserved.