Gravity-driven flow and heat transfer in a spent nuclear fuel storage pool
Description
The GFLOW code analyzes a three-dimensional rectangular porous medium by dividing the porous medium into a number of nodes or cells specified by the user. The finite difference form of the fluid conservation equations is solved for each node by application of a modified ''marker and cell'' numerical technique. The existence of spent nuclear fuel in any node is modeled by using a porosity value less than unity in that node and by including a surface heat transfer term in the fluid energy equation. In addition, local pressure losses due to grid spaces or other planar flow obstructions can be modeled by local loss coefficients. Heat conduction in the fuel is simulated by a fast running implicit finite difference model of the fuel, gap, and clad regions of the fuel rod
Additional details
Publishing Information
- Journal Title
- Nucl. Sci. Eng.
- Journal Volume
- 83
- Journal Issue
- 1
- Series
- Nucl. Sci. Eng.
- Journal Page Range
- 1-12
- ISSN
- 0029-5639
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15009833
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- COMPUTER CODES; FINITE DIFFERENCE METHOD; FLUID FLOW; FUEL RODS; FUEL STORAGE POOLS; GRAVITATION; HEAT TRANSFER; POROSITY; POROUS MATERIALS; SPENT FUEL STORAGE; THERMAL CONDUCTION; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ENERGY TRANSFER; FUEL ELEMENTS; ITERATIVE METHODS; MATERIALS; NUMERICAL SOLUTION; REACTOR COMPONENTS; STORAGE