Power-Cooling-Mismatch Test Series Test PCM-7. Experiment operating specifications. [PWR]
Technical Report
·
OSTI ID:6179135
The experiment operating specifications for the Power-Cooling-Mismatch (PCM) Test PCM-7 to be conducted in the Power Burst Facility are described. The PCM Test Series was designed on the basis of a parametric evaluation of fuel behavior response with cladding temperature, rod internal pressure, time in film boiling, and test rod power being the variable parameters. The test matrix, defined in the PCM Experiment Requirements Document (ERD), encompasses a wide range of situations extending from pre-CHF (critical heat flux) PCMs to long duration operation in stable film boiling leading to rod failure.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6179135
- Report Number(s):
- TFBP-TR-311
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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POWER DISTRIBUTION
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REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY
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TEMPERATURE GRADIENTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HYDRAULICS
MECHANICS
PBF REACTOR
PERFORMANCE TESTING
POWER DISTRIBUTION
POWER-COOLING-MISMATCH ACCIDENTS
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY
REACTORS
SAFETY
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS