PBF--LOCA test series test LOC-11 experiment operating specification. [PWR]
Technical Report
·
OSTI ID:6439433
The PBF--LOCA fuel behavior program is one of several test programs being conducted to provide experimental information on the behavior of nuclear reactor fuels under normal, off-normal and accident conditions in the Power Burst Facility at the Idaho National Engineering Laboratory. Specifically, the PBF--LOCA Program will obtain data for analytical model development and verification, and determine the behavior of fuel rods when exposed to a wide variety of loss-of-coolant (LOCA) conditions. A test description, detailed operating specifications, data acquisition requirements, and posttest data reductions requirements for Test LOC-11 are presented.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6439433
- Report Number(s):
- TFBP-TR-209
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FUEL ASSEMBLIES
LOSS OF COOLANT
PBF REACTOR
PERFORMANCE TESTING
PRESSURE GRADIENTS
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
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REACTORS
SAFETY
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TESTING
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
FUEL ASSEMBLIES
LOSS OF COOLANT
PBF REACTOR
PERFORMANCE TESTING
PRESSURE GRADIENTS
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