Evaluation of a detailed radiation heat transfer model in a high temperature reactor systems simulation model
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 (HTRs) 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 was developed and also implemented in the Flownex reactor model. This paper also describes the analytical formulae for view factor calculation in this detailed radiation heat transfer model. The HTR-10 and the 268 MW version of the PBMR were used as case studies in which Loss-of-Flow events without SCRAM were simulated. In these simulations, the time to reach recriticality was used as an indicator of heat removal effectiveness. With the HTR-10, other non-linear 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 268 MW PBMR DLOFC, the use of a detailed radiation model increased solution time with 30%. With both the HTR-10 and the PBMR, the radiation model had negligible effect on the total heat resistance from the reactor, as indicated by the time elapsed until recriticality. For system simulation codes that focus on transient response of a plant, it is not considered worthwhile to use a detailed radiation model, as the gain in accuracy does not justify the increased solution time or the implementation and verification effort
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2008.02.020Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2008.02.020;
- PII
- S0029-5493(08)00137-4;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 11
- Journal Page Range
- p. 2985-2994
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 3. international topical meeting on high temperature reactor technology
- Acronym
- HTR-2006
- Dates
- 1-5 Oct 2006
- Place
- Johannesburg (South Africa)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40053115
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; COMPUTERIZED SIMULATION; EVALUATION; HEAT; HEAT TRANSFER; HTGR TYPE REACTORS; LOSS OF FLOW; MATHEMATICAL SOLUTIONS; REACTOR ACCIDENT SIMULATION; REACTOR CORES; SCRAM; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; ENERGY; ENERGY TRANSFER; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; SIMULATION
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.