Published 1984
| Version v1
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Restricted
Radiation heat transfer model for the SCDAP code
Description
A radiation heat transfer model has been developed for severe fuel damage analysis which accounts for anisotropic effects of reflected radiation. The model simplifies the view factor calculation which results in significant savings in computational cost with little loss of accuracy. Radiation heat transfer rates calculated by the isotropic and anisotropic models compare reasonably well with those calculated by other models. The model is applied to an experimental nuclear rod bundle during a slow boiloff of the coolant liquid, a situation encountered during a loss of coolant accident with severe fuel damage. At lower temperatures and also lower temperature gradients in the core, the anisotropic effect was not found to be significant
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI85004718.
Files
Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- EGG-M--11084
Conference
- Title
- ASME winter annual meeting.
- Dates
- 9-13 Dec 1984.
- Place
- New Orleans, LA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16064786
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANISOTROPY; COMPUTER CODES; COST; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAT TRANSFER; ISOTROPY; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR SAFETY; REACTOR TECHNOLOGY
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-841201--28.