Molten fuel containment analysis for SLSF experiments. [LMFBR]
The Sodium Loop Safety Facility (SLSF) experiments are being conducted in the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory to furnish information concerning the behavior of fast reactor fuel elements under a hypothesized loss-of-flow accident conditions. These experiments involve measurements and observations that will permit an assessment of the location and time of sodium void initiation, the nature of sodium expulsion and reentry, the time and nature of cladding failure and motion, the molten fuel motion, and the extent of flow plugging by molten fuel freezing at the axial extremities of the subassembly. Because such high energy experiments are being conducted in-pile within the ETR facility, extensive pretest analysis was required to ensure loop integrity. One aspect of this analysis, which is the subject of this paper, was the assessment of molten fuel relocation and refreezing on the wall of the SLSF.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5981990
- Report Number(s):
- CONF-791103-25
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
BREEDER REACTORS
CORIUM
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
MELTDOWN
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE DISTRIBUTION