Thermal-hydraulic analysis of spent fuel storage systems
This paper describes the COBRA-SFS (Spent Fuel Storage) computer code, which is designed to predict flow and temperature distributions in spent nuclear fuel storage and transportation systems. The decay heat generated by spent fuel in a dry storage cask is removed through a combination of conduction, natural convection, and thermal radiation. One major advantage of COBRA-SFS is that fluid recirculation within the cask is computed directly by solving the mass and momentum conservation equations. In addition, thermal radiation heat transfer is modeled using detailed radiation exchange factors based on quarter-rod segments. The equations governing mass, momentum, and energy conservation for incompressible flows are presented, and the semi-implicit solution method is described. COBRA-SFS predictions are compared to temperature data from a spent fuel storage cask test and the effect of different fill media on the cladding temperature distribution is discussed. The effect of spent fuel consolidation on cask thermal performance is also investigated. 16 refs., 6 figs., 2 tabs.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5999921
- Report Number(s):
- PNL-SA-14444; CONF-870816-28; ON: DE88000562
- Resource Relation:
- Conference: 24. national heat transfer conference and exhibition, Pittsburgh, PA, USA, 9 Aug 1987; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
COBRA-SFS (Spent Fuel Storage): A thermal-hydraulic analysis computer code: Volume 1, Mathematical models and solution method
Cask consolidated spent fuel thermal analyses using the COBRA-SFS code
Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
SPENT FUEL STORAGE
HEAT TRANSFER
HYDRAULICS
TEMPERATURE DISTRIBUTION
C CODES
COMPUTER CODES
DRY STORAGE
EQUATIONS
FLUID FLOW
SPENT FUEL CASKS
CASKS
CONTAINERS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
STORAGE
050900* - Nuclear Fuels- Transport
Handling
& Storage
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)