Calculation Aspects of Detailed Radiation Heat Transfer
Creators
- 1. School for Mechanical Engineering, Northwest University, Private Bag X6001, Potchefstroom 2520 (South Africa)
- 2. Postgraduate School for Nuclear Engineering, North-West University (South Africa)
Description
Radiation heat transfer is a major mode of heat transfer in High Temperature Gas-cooled Reactors because of the high operating temperatures. It is however a difficult phenomenon to calculate in full detail due to its geometrical complexity. One has to use either a numerical method or complex analytical view factor formulae. Except the difficulty of view factor calculation, a vast number of calculation elements are required to consider all interacting surfaces around a cavity. A common approximation in systems simulation codes is to connect only directly opposing surfaces with a view factor of one. The accuracy of this approximation was investigated with a finite volume, two-dimensional axial-symmetric reactor model implemented in the systems simulation code Flownex. A detailed radiation model using analytical formulae [1] for view factor calculation was also implemented with the HTR-10 as well as the 268MW version of the PBMR used as case studies. Loss-of-Flow events without SCRAM were simulated and the time to recriticality used as indicator of heat removal effectiveness. With the HTR-10, other nonlinear phenomena in the reactor core constrained the solution process, so that the number of radiation elements had no effect on solution time, while with the 268MW PBMR DLOFC, the use of a detailed radiation model increased solution time with 30 percent. (author)
Files
54081948.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- INIS-ZA--23M0064
Conference
- Title
- 3. International Topical Meeting on High Temperature Reactor Technology
- Dates
- 1-5 Oct 2006
- Place
- Johannesburg (South Africa)
INIS
- Country of Publication
- South Africa
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54081948
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; APPROXIMATIONS; FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; HEAT TRANSFER; HTGR TYPE REACTORS; LOSS OF FLOW; REACTOR CORES; SIMULATION; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; DEVELOPED COUNTRIES; ENERGY TRANSFER; EUROPE; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; NATIONAL ORGANIZATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TEMPERATURE RANGE; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; 5 refs., 11 figs.