Crust-formation and refreezing model for molten-fuel/concrete interaction codes. [PWR; BWR]
Conference
·
OSTI ID:5845586
There is a class of hypothetical core-melt accidents in nuclear reactors in which molten core materials are deposited into the concrete reactor cavity, resulting in a vigorous thermal attack on the concrete. The temperature of the pool is maintained at a point where heat losses to concrete and to surroundings above the pool approximately balance heat gains from decay of fission products. During the early stages while the pool is fully molten, the dominant heat-transfer process within the pool is convection. At later times, this changes as temperatures fall and refreezing begins. The existing CORCON-MOD1 code, which does not allow these refreezing effects, is being modified to account for the changes in heat-transfer behavior as refreezing takes place.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5845586
- Report Number(s):
- SAND-83-0831C; CONF-830816-14; ON: DE83016201
- Country of Publication:
- United States
- Language:
- English
Similar Records
Modelling of molten fuel/concrete interactions. [PWR; BWR]
Modeling of molten corium-concrete interaction: Interim report
CORCON: molten-fuel/concrete interactions code
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5395762
Modeling of molten corium-concrete interaction: Interim report
Technical Report
·
Tue Sep 01 00:00:00 EDT 1987
·
OSTI ID:6100796
CORCON: molten-fuel/concrete interactions code
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6756645
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATERIALS
MATHEMATICAL MODELS
MECHANICS
MELTDOWN
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SOLIDIFICATION
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATERIALS
MATHEMATICAL MODELS
MECHANICS
MELTDOWN
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SOLIDIFICATION
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS