Plugging of intersubassembly gaps by downward flowing molten steel. [LMFBR]
Conference
·
OSTI ID:6925799
In the assessment of the meltout phase of an LMFBR hypothetical core disruptive accident, a pathway for the escape of molten fuel from the disrupted core is provided by the narrow channels separating adjacent subassemblies. However, the removal of fuel through intersubassembly gaps might be impeded by steel blockage formation, if molten steel is postulated to enter the gap network ahead of disrupted fuel. Reported here are the results of an analysis of the conduction freezing controlled penetration behavior of molten steel flowing downward through the voided (of sodium) gap channels nominally separating adjacent subassemblies below the active core region. The objective is to determine the range of conditions under which the steel is predicted to be deposited as a thin crust on the channel walls leaving an open pathway remaining for subsequent fuel flow instead of forming a complete plug which closes off the gap channel and obstructs fuel removal immediately thereafter.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6925799
- Report Number(s):
- CONF-840614-38; ON: DE84006744
- Country of Publication:
- United States
- Language:
- English
Similar Records
Results of the GAP-4 experiment on molten-fuel drainage through intersubassembly gap geometry. [LMFBR]
Intersubassembly fuel penetration into a failed blanket subassembly. [LMFBR]
Intersubassembly fuel penetration into a failed primary control subassembly in an LMFBR
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5866935
Intersubassembly fuel penetration into a failed blanket subassembly. [LMFBR]
Technical Report
·
Sun Aug 01 00:00:00 EDT 1982
·
OSTI ID:6809665
Intersubassembly fuel penetration into a failed primary control subassembly in an LMFBR
Technical Report
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:5323606
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
CORIUM
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FLUID MECHANICS
FUEL ASSEMBLIES
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
MELTDOWN
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
CORIUM
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FLUID MECHANICS
FUEL ASSEMBLIES
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
MELTDOWN
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY