Actions for Burnout conditions in BSR cores under forced convection flow
Burnout conditions in BSR cores under forced convection flow
- Author
- Binford, F. T.
- Published
- United States : [publisher not identified], 1978.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1978. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Summary
- The BSR normally operates at a power level of two megawatts with a downward forced convection cooling flow of about 1000 gallons per minute. Because of the relatively low downward coolant velocity, one or two feet per second, the bouyancy produced by the heating of the water as it passes through the core may result in a significant reduction in the critical heat flux as determined by the usual forced convection correlation methods. Previous estimates of the critical heat flux have not taken this bouyancy effect into consideration. It is the purpose of this study to develop a suitable method for estimating the relationship between flow and power level which permits the establishment of limits on operating parameters adequate to prevent burnout and to apply these to the operation of the BSR.
- Report Numbers
- ORNL/TM-2231/S1
- Other Subject(s)
- 21 specific nuclear reactors and associated plants
- 220600 - nuclear reactor technology- research, test & experimental reactors
- Bsr-2 reactor
- Burnout
- Critical heat flux
- Enriched uranium reactors
- Fluid flow
- Heat flux
- Pool type reactors
- Reactor components
- Reactor cores
- Reactors
- Research and test reactors
- Research reactors
- Temperature distribution
- Thermal reactors
- Water cooled reactors
- Water moderated reactors
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: W-7405-ENG-26
OSTI Identifier 6793276
Research organization: Oak Ridge National Lab., Tenn. (USA).
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