Analysis of Closed-Pool Boilup Using the TRANSIT-HYDRO Code. [LMFBR]
Conference
·
OSTI ID:6112741
- Argonne National Laboratory (ANL), Argonne, IL (United States)
The benign termination of the transition phase of a hypothetical LMFBR accident rest on the avoidance of highly energetic recriticalities prior to escape of bottled molten core materials from the active core region. In scenarios where molten fuel is trapped due to axial blockages, the maintenance of subcritical configurations until radial flow paths develop requires stable boil-up of the molten fuel/steel mixture. This paper describes the analysis of an experiment investigating the behavior of closed boiling pools using the two-fluid hydrodynamics module of TRANSIT-HYDRO, a deterministic transition-phase analysis code.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6112741
- Report Number(s):
- CONF-830609--69; ON: DE85004815
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
Analysis
BREEDER REACTORS
Behavior
CORIUM
CRITICALITY
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
Nuclear Criticality Safety Program (NCSP)
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
VOID FRACTION