Study of strongly heated upward turbulent gas flow - 14089
Creators
- 1. Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)
- 2. Department of Nuclear Engineering, Khalifa University of Science, Technology and Research - Kustar, P.O.Box 127788, Abu Dhabi (United Arab Emirates)
Description
In vertical upward heated flow which is reactor core typical flow configuration, turbulent heat transfer can be deteriorated if the flow is going from forced convection to mixed convection regime which is a phenomenon that can happen during an accident phase. It has been found that Gas-cooled Fast Reactor (GFR) might operate in the deteriorated turbulent heat transfer (DTHT) regime during an accident phase. Several previous works have been done to investigate and describe the phenomenon that occurs in mixed convection regime. This paper will first discuss about the heat transfer regimes that exist and their effect on turbulent heat transfer. Some of the natural circulation data from an experiment will be compared to the numerical results. The problem domain for the CFD analysis is made to represent the experiment of the natural circulation which is the condition that of the reactor core during accidents. The v2-f model is chosen as the turbulence model for this case because it has been proven to perform well for mixed convection case. Through a numerical analysis, the phenomena can be reasonably depicted. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-776-7
- Imprint Pagination
- 9 p.
Conference
- Title
- International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP 2014
- Dates
- 6-9 Apr 2014
- Place
- Charlotte, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54022484
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAST REACTORS; FORCED CONVECTION; GAS FLOW; NATURAL CONVECTION; NUMERICAL ANALYSIS; REACTOR ACCIDENTS; REACTOR CORES; TURBULENCE
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; MATHEMATICS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 17 refs.; Available on CD-ROM from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)