Melt coolability modeling and comparison to MACE test results
Conference
·
OSTI ID:5509026
An important question in the assessment of severe accidents in light water nuclear reactors is the ability of water to quench a molten corium-concrete interaction and thereby terminate the accident progression. As part of the Melt Attack and Coolability Experiment (MACE) Program, phenomenological models of the corium quenching process are under development. The modeling approach considers both bulk cooldown and crust-limited heat transfer regimes, as well as criteria for the pool thermal hydraulic conditions which separate the two regimes. The model is then compared with results of the MACE experiments.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- EPRI; Electric Power Research Inst., Palo Alto, CA (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5509026
- Report Number(s):
- ANL/CP-75620; CONF-9204105-4; ON: DE92010506; CNN: RP3047-08
- Resource Relation:
- Conference: 2. Organization for Economic Cooperation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) specialists meeting, Karlsruhe (Germany), 1-3 Apr 1992
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BWR TYPE REACTORS
REACTOR ACCIDENTS
CORIUM
QUENCHING
PWR TYPE REACTORS
CONCRETES
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
INTERACTIONS
MATHEMATICAL MODELS
REACTOR SAFETY
ACCIDENTS
BUILDING MATERIALS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
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POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
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Light-Water Moderated
Boiling Water Cooled
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BWR TYPE REACTORS
REACTOR ACCIDENTS
CORIUM
QUENCHING
PWR TYPE REACTORS
CONCRETES
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
INTERACTIONS
MATHEMATICAL MODELS
REACTOR SAFETY
ACCIDENTS
BUILDING MATERIALS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MATERIALS
MECHANICS
POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
990200 - Mathematics & Computers