Coolant pressure distribution in wire-wrapped rod bundles
Conference
·
OSTI ID:5489101
To analyze thermal-hydraulic behavior in a wire-wrapped fuel or blanket assembly, it is necessary to evaluate the coolant flow field in the rod bundle. Evaluation of the coolant flow phenomenon in the wire-wrapped assembly becomes even more important when the bundle has a low pitch-to-diameter ratio or a wire-wrap configuration different from the current reference straight-start design or the assembly is located in a high radial power gradient region in a reactor. Subchannel analysis method (FULMIX-II) was developed to specifically treat the complex coolant transfer process within a wire-wrapped assembly and to determine the coolant temperature field accordingly.
- Research Organization:
- General Electric Co., Sunnyvale, CA (USA). Advanced Reactor Systems Dept.
- DOE Contract Number:
- EY-76-C-03-0893-031
- OSTI ID:
- 5489101
- Report Number(s):
- GEFR-SP-193; CONF-800607-17
- Country of Publication:
- United States
- Language:
- English
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