Preliminary ECC delivery data at 1/15-scale. Quarterly progress report, January 1, 1976--March 31, 1976. [PWR].
- Author
- Block, J. A.
- Published
- United States : [publisher not identified], 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Crowley, C. J.
- Summary
- Preliminary test results in a 1/15-scale, cylindrical, elevated pressure, PWR-model test vessel are described. These tests form part of a program to develop an analytical and empirical model for plenum filling. During the quarter, countercurrent flow, lower plenum voiding, and super-heated-wall-with-countercurrent-flow tests were conducted. Sample data comparing trends with past data in a different geometry are presented. Good agreement is demonstrated. Special interest items of pressure drop measurements, oscillatory water delivery, steam and water injection sequencing and elevated pressure control are discussed.
- Report Numbers
- CREARE-TN-235
- Other Subject(s)
- 21 specific nuclear reactors and associated plants
- 210200 - power reactors, nonbreeding, light-water moderated, nonboiling water cooled
- 22 general studies of nuclear reactors
- 220900 - nuclear reactor technology- reactor safety
- Accidents
- Eccs
- Engineered safety systems
- Fluid mechanics
- Hydraulics
- Loss of coolant
- Mechanics
- Performance testing
- Pressure drop
- Pwr type reactors
- Reactor accidents
- Reactor protection systems
- Reactors
- Research programs
- Simulation
- Testing
- Water cooled reactors
- Water moderated reactors
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: AT(49-24)-0162
OSTI Identifier 7345883
Research organization: Creare, Inc., Hanover, N.H. (USA).
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