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; TRN: 80-009389
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Las Vegas, NV, USA, 8 Jun 1980
- Country of Publication:
- United States
- Language:
- English
Similar Records
A study of molten debris freezing and wall erosion in the RIA-ST-4 experiment
Reactivity Initiated Accident Test Series RIA Scoping Test Quick Look Report
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
MELTDOWN
ROD DROP ACCIDENTS
CORIUM
SOLIDIFICATION
HYDRAULICS
PWR TYPE REACTORS
ROD EJECTION ACCIDENTS
SIMULATION
HEAT TRANSFER
LIQUID FLOW
REACTOR SAFETY
TEMPERATURE GRADIENTS
URANIUM DIOXIDE
ZIRCALOY
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
MECHANICS
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTORS
SAFETY
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled