Thermal behavior of concrete. [LMFBR]
Conference
·
OSTI ID:7279263
The treatment of post accident containment problems requires an understanding of concrete when subjected to high temperatures due to thermal contact with molten core materials and/or coolant. Sodium spills on concrete are of special concern because the resulting chemical reactions are collectively exothermic. Among other possible safety problems, the gas released by the thermal decomposition of concrete has the potential of producing pressures sufficient to endanger the integrity of cell liners. Insight into these phenomena has been gained by constructing a computer model and performing a series of studies. The code presently calculates the following quantities as functions of space and time: (1) temperature of the cell liner, (2) temperature of the concrete, (3) ablation rate of the heated concrete surface, (4) the water, water vapor, and carbon dioxide evolution rates, (5) the total gas discharged, and (6) the decomposition energy absorption rate for each decomposing species. The code has been used to predict the decomposition of concrete both with and without a containment liner.
- Research Organization:
- Sandia Labs., Albuquerque, N.Mex. (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 7279263
- Report Number(s):
- SAND-77-1093C; CONF-771109-18
- Country of Publication:
- United States
- Language:
- English
Similar Records
Time-resolved penetration measurements of liquid sodium into limestone concrete
Exploratory study of molten core material/concrete interactions, July 1975--March 1977. [BWR; PWR]
Assessment of models for steam release from concrete and implications for modeling corium behavior in reactor cavities
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6871862
Exploratory study of molten core material/concrete interactions, July 1975--March 1977. [BWR; PWR]
Technical Report
·
Tue Jan 31 23:00:00 EST 1978
·
OSTI ID:5073998
Assessment of models for steam release from concrete and implications for modeling corium behavior in reactor cavities
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6827807
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
36 MATERIALS SCIENCE
360604 -- Materials-- Corrosion
Erosion
& Degradation
ACCIDENTS
ALKALI METALS
BREEDER REACTORS
BUILDING MATERIALS
CHEMICAL REACTIONS
CONCRETES
CONTAINMENT
DECOMPOSITION
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MATHEMATICAL MODELS
MELTDOWN
METALS
REACTOR ACCIDENTS
REACTORS
SODIUM
TEMPERATURE DEPENDENCE
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360604 -- Materials-- Corrosion
Erosion
& Degradation
ACCIDENTS
ALKALI METALS
BREEDER REACTORS
BUILDING MATERIALS
CHEMICAL REACTIONS
CONCRETES
CONTAINMENT
DECOMPOSITION
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MATHEMATICAL MODELS
MELTDOWN
METALS
REACTOR ACCIDENTS
REACTORS
SODIUM
TEMPERATURE DEPENDENCE