PRELIMINARY BOILING BURNOUT EXPERIMENTS WITH A 19-ROD BUNDLE GEOMETRY IN AXIAL FLOW
Technical Report
·
OSTI ID:4793265
Boiling burnout heat flux data were obtained with an electrically heated model of a 19-rod bundle nuclear reactor fuel assembly in a cylindrical tube for vertical upward flow of water at 1200 psig. Heat was generated in the test section by d-c electrical resistance heating. Mass flow rates were ties ranged from 0 to 29 wt% steam. The resultant data are compared with independent data for a 19-rod bundle. (auth)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-16-027192
- OSTI ID:
- 4793265
- Report Number(s):
- HW-73395
- Country of Publication:
- United States
- Language:
- English
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