Intersubassembly fuel penetration into a failed blanket subassembly. [LMFBR]
This work provides additional understanding of hypothetical core-disruptive accident issues involving LMFBRs. Intersubassembly molten fuel and steel penetration into a failed blanket subassembly was analyzed with the two-dimensional SIMMER-II code. Interaction of the fuel and steel with the blanket coolant was included in the investigation. The molten core material was injected through a prescribed opening in the blanket subassembly wall. Eighteen cases involving variations of parameters of importance to the subsequent flow were calculated. In general the resulting pressurization was a good figure of merit for rating the severity of the events. In turn, the pressurization depended on the wall opening size, the initial pool pressure, and the heat-transfer rates. However, only when the wall failure rate was large relative to the sodium expulsion rate, was sufficient pressure generated that could affect the reactor vessel containment.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6809665
- Report Number(s):
- LA-9436-MS; ON: DE82021255
- Country of Publication:
- United States
- Language:
- English
Similar Records
Intersubassembly fuel penetration into a failed primary control subassembly in an LMFBR
Plugging of intersubassembly gaps by downward flowing molten steel. [LMFBR]
Fuel penetration of intersubassembly gaps in LMFBRs: a calculational method with the SIMMER-II code
Technical Report
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:5323606
Plugging of intersubassembly gaps by downward flowing molten steel. [LMFBR]
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6925799
Fuel penetration of intersubassembly gaps in LMFBRs: a calculational method with the SIMMER-II code
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6977640
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
ALKALI METALS
BREEDER REACTORS
CORIUM
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
MELTDOWN
METALS
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
SODIUM
STRESSES
THERMAL STRESSES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
BREEDER REACTORS
CORIUM
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
MELTDOWN
METALS
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
SODIUM
STRESSES
THERMAL STRESSES