Vapor explosion in the RIA-ST-4 experiment. [BWR]
Conference
·
OSTI ID:5526517
A concern in assuring the safety of commercial light water reactors (LWRs) is whether core overheating, during which molten fuel is produced, can lead to massive vaporization of the coolant and shock pressurization of the system due to an energetic molten fuel-coolant interaction (MFCI). The RIA-ST-4 experiment was one of four scoping tests in the Reactivity Initiated Accident (RIA) Test Series which is being conducted in the Power Burst Facility (PBF) to define an energy deposition failure threshold and to determine modes and consequences of fuel rod failure during a postulated boiling water reactor (BWR) control rod drop accident.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5526517
- Report Number(s):
- CONF-800607--16
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
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MOCKUP
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OXYGEN COMPOUNDS
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REACTIVITY
REACTIVITY INSERTIONS
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REACTOR SAFETY
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WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
BWR TYPE REACTORS
CHALCOGENIDES
EXPLOSIONS
FUEL ELEMENTS
FUEL RODS
FUEL-COOLANT INTERACTIONS
MELTDOWN
MOCKUP
OXIDES
OXYGEN COMPOUNDS
PRESSURE GRADIENTS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
ROD DROP ACCIDENTS
SAFETY
STRUCTURAL MODELS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS