Published June 2018
| Version v1
Journal article
Thermal hydraulic-analysis of the convective heat transfer of an air-cooled BWR spent fuel assembly
- 1. Technische Univ. Dresden (Germany). Chair of Hydrogen and Nuclear Energy
Description
Since the reactor accident in Fukushima Daiichi, the vulnerability of spent fuel pools (SFP) is more focused in nuclear safety research. This paper presents the experimental findings about the convective heat transfer of a boiling water reactor (BWR) spent FA under the absence of water. These studies are performed within the joint project SINABEL that is funded by the German Federal Ministry of Education and Research to investigate the thermal hydraulics of selected accident scenarios in SFP experimentally and numerically.
Additional details
Publishing Information
- Journal Title
- Atw. Internationale Zeitschrift fuer Kernenergie
- Journal Volume
- 63
- Journal Issue
- 6-7
- Journal Page Range
- p. 397-401
- ISSN
- 1431-5254
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 49076232
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BWR TYPE REACTORS; CONVECTION; FUEL ASSEMBLIES; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LOSS OF COOLANT; SPATIAL DISTRIBUTION; SPENT FUELS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ASSEMBLIES; FUELS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MATERIALS; MECHANICS; NUCLEAR FUELS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS