Containment analysis capabilities of CONTEMPT4/MOD2. [PWR]
The safety assessment and licensing of nuclear reactor plants by the United States Nuclear Regulatory Commission (USNRC) depend partially on analytical computer programs to predict the response of safeguard systems to accident conditions. CONTEMPT4/MOD2 is a new computer code to predict the long-term thermal hydraulic behavior of water-cooled nuclear reactor containment systems during postulated loss-of-coolant accident (LOCA) conditions. Written in FORTRAN IV, the new code was developed at the Idaho National Engineering Laboratory by EG and G Idaho, Inc., under the sponsorship of the USNRC. The paper describes the features and analytical models available in the code. Comparisons of calculated results with experimental data are also presented which demonstrate the range of containment problems applicable to CONTEMPT4/MOD2.
- Research Organization:
- EDS Nuclear, Inc., San Francisco, CA (USA); Sargent and Lundy, Chicago, IL (USA); EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6797673
- Report Number(s):
- CONF-781022-15
- Country of Publication:
- United States
- Language:
- English
Similar Records
CONTEMPT4/MOD2: a multicompartment containment system analysis program. [PWR]
CONTEMPT4/MOD2; multicompartment containment. [CDC7600; FORTRAN IV (96%) and COMPASS (4%)]
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
C CODES
COMPUTER CALCULATIONS
COMPUTER CODES
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS