Exploratory study of molten core material/concrete interactions, July 1975--March 1977. [BWR; PWR]
An experimental study of the interaction between high-temperature molten materials and structural concrete is described. The experimental efforts focused on the interaction of melts of reactor core materials weighing 12 to 200 kg at temperatures 1700 to 2800/sup 0/C with calcareous and basaltic concrete representative of that found in existing light-water nuclear reactors. Observations concerning the rate and mode of melt penetration into concrete, the nature and generation rate of gases liberated during the interaction, and heat transfer from the melt to the concrete are described. Concrete erosion is shown to be primarily a melting process with little contribution from mechanical spallation. Water and carbon dioxide thermally released from the concrete are extensively reduced to hydrogen and carbon monoxide. Heat transfer from the melt to the concrete is shown to be dependent on gas generation rate and crucible geometry. Interpretation of results from the interaction experiments is supported by separate studies of the thermal decomposition of concretes, response of bulk concrete to intense heat fluxes (28 to 280 W/cm/sup 2/), and heat transfer from molten materials to decomposing solids. The experimental results are compared to assumptions made in previous analytic studies of core meltdown accidents in light-water nuclear reactors. A preliminary computer code, INTER, which models and extrapolates results of the experimental program is described. The code allows estimation of the effect of physical parameters on the nature of the melt/concrete interaction.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 5073998
- Report Number(s):
- SAND-77-2042; TRN: 78-010672
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
MELTDOWN
CONCRETES
DECOMPOSITION
CORIUM
CHEMICAL REACTION KINETICS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
HEAT TRANSFER
MATHEMATICAL MODELS
SIMULATION
VERY HIGH TEMPERATURE
ACCIDENTS
BUILDING MATERIALS
CHEMICAL REACTIONS
ENERGY TRANSFER
KINETICS
MATERIALS
REACTION KINETICS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360604 - Materials- Corrosion
Erosion
& Degradation