Published 1985
| Version v1
Journal article
Radiative heat transfer in a PWR fuel bundle under accident conditions
Description
A simple model is applied for the analysis of radiative heat transfer in a PWR fuel assembly in regular operation and under a loss of coolant accident. The method includes a matrix calculation of view factors, performed dividing the bundle into unit cells composed by portions of fuel rods and by a coolant subchannel. The cells are correlated considering imaginary faces among them, and the pertinent equations are simultaneously solved for the whole assembly. Some results are related for various values of the heat flux in different operational situations
Additional details
Publishing Information
- Journal Title
- Ing. Nucl.
- Journal Issue
- 5-6
- Series
- Ing. Nucl.
- ISSN
- 0020-0972
- CODEN
- INNUA
INIS
- Country of Publication
- Italy
- Country of Input or Organization
- Italy
- INIS RN
- 17013358
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LOSS OF COOLANT; LOSS OF FLOW; PWR TYPE REACTORS; REACTOR CORES
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS