Study of turbulent natural-circulation flow and low-Prandtl-number forced-convection flow
Description
Calculational methods and results are discussed for the coupled energy and momentum equations of turbulent natural circulation flow and low Prandtl number forced convection flow. The objective of this paper is to develop a calculational method for the study of the thermal-hydraulic behavior of coolant flowing in a liquid metal fast breeder reactor channel under natural circulation conditions. The two-equation turbulence model is used to evaluate the turbulent momentum transport property. Because the analogy between momentum transfer and heat transfer does not generally hold for low Prandtl number fluid and natural circulation flow conditions, the turbulent thermal conductivity is calculated independently using equations similar to the two-equation turbulence model. The numerical technique used in the calculation is the finite element method
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
12627019.pdf
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Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- CONF-800723--27
Conference
- Title
- 19. national heat transfer conference.
- Dates
- 27 - 30 Jul 1980.
- Place
- Orlando, FL, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12627019
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; FINITE ELEMENT METHOD; FORCED CONVECTION; HYDRAULICS; LMFBR TYPE REACTORS; LOSS OF FLOW; MATHEMATICAL MODELS; NATURAL CONVECTION; PRANDTL NUMBER; REACTOR SAFETY; TURBULENT FLOW
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; CONVECTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; NUMERICAL SOLUTION; REACTOR ACCIDENTS; REACTORS; SAFETY