Containment accident analysis using CONTEMPT4/M0D2 compared with experimental data. [PWR]
Conference
·
OSTI ID:6703175
CONTEMPT4/MOD2 is a new computer program developed to predict the long-term thermal hydraulic behavior of light-water reactor and experimental containment systems during postulated loss-of-coolant accident (LOCA) conditions. Improvements over previous containment codes include multicompartment capability and ice condenser analytical models. A program description and comparisons of calculated results with experimental data are presented.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6703175
- Report Number(s):
- CONF-780622-31
- Country of Publication:
- United States
- Language:
- English
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Sat Dec 31 23:00:00 EST 1977
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Tue Jan 31 23:00:00 EST 1978
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
C CODES
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
COMPUTER CODES
CONTAINMENT
CONTAINMENT SYSTEMS
DATA
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
C CODES
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
COMPUTER CODES
CONTAINMENT
CONTAINMENT SYSTEMS
DATA
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS