Fuel pins and core response under LMFBR top accident conditions
Conference
·
OSTI ID:6494431
Out-of-reactor experiments are currently being performed at Argonne National Laboratory to examine fuel sweepout and related post-failure phenomena under hypothetical TOP accident conditions. These tests are supplementing the TREAT MARK-II loop data base by keying on effects of important parameter variations such as system hydraulics and intrabundle coherency. In these tests, molten UO/sub 2/, generated by a thermite reaction at 3470/sup 0/K, is injected over approximately 40 msec into flowing sodium in a bundle of simulated LMFBR-type fuel pins. Hydraulic conditions in the bundle are selected to match conditions in either the MARK-II loop (HUMP-series) or the current design LMFBR subassembly (CAMEL-series). To date, four tests have been performed in both single-pin and seven-pin configurations representing coherent and incoherent subassembly power-to-flow cases, respectively. Details of the fuel motion were observed using a flash x-ray cine system. A compilation of significant findings from the four sweepout tests is presented.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA); General Electric Co., Sunnyvale, CA (USA); Argonne National Lab., IL (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6494431
- Report Number(s):
- HEDL-SA-1500-FP; CONF-781022-38
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
DATA
DATA FORMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FLOW RATE
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENT FAILURE
FUEL-COOLANT INTERACTIONS
GRAPHS
HYDRAULICS
INFORMATION
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENT OVERPOWER ACCIDENTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
DATA
DATA FORMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FLOW RATE
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENT FAILURE
FUEL-COOLANT INTERACTIONS
GRAPHS
HYDRAULICS
INFORMATION
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENT OVERPOWER ACCIDENTS