Published January 1983 | Version v1
Journal article

Gravity-driven flow and heat transfer in a spent nuclear fuel storage pool

Creators

  • 1. NUS Corporation, 2740 Sand Hill Road, Menlo Park, California 94025

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