Assessment of molten debris freezing in a severe RIA in-pile test. [PWR; BWR]
An understanding of the freezing of molten debris on cold core structures following a hypothetical core meltdown accident in a light water reactor (LWR) is of importance to reactor safety analysis. The purpose of the present investigation was to analyze the transient freezing of the molten debris produced in a severe reactivity initiated accident (RIA) scoping test, designated RIA-ST-4, which was performed in the Power Burst Facility and simulated a BWR control rod drop accident. In the RIA-ST-4 experiment, a single, unirradiated, 20 wt % enriched, UO/sub 2/ fuel rod contained within a Zircaloy flow shroud was subjected to a single power burst which deposited a total energy of about 700 cal/g UO/sub 2/. This energy deposition is well above what is possible in a commercial LWR during a hypothetical control rod drop (BWR) or ejection (PWR) accident. However, the performance of such an in-pile test has provided important information regarding molten debris movement, relocation, and freezing on cold walls.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5334898
- Report Number(s):
- CONF-800607--15
- Country of Publication:
- United States
- Language:
- English
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210200 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
CORIUM
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID FLOW
MECHANICS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
ROD DROP ACCIDENTS
ROD EJECTION ACCIDENTS
SAFETY
SIMULATION
SOLIDIFICATION
TEMPERATURE GRADIENTS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS