CONTEMPT-LT/028; CONTEMPT-LT/026; pressure-temperature response. [CDC7600,CYBER176; IBM360; FORTRAN IV and COMPASS (CDC7600), FORTRAN IV and BAL (IBM360)]
CONTEMPT-LT was developed to predict the long-term behavior of water-cooled nuclear reactor containment systems subjected to postulated loss-of-coolant accident (LOCA) conditions. CONTEMPT-LT calculates the time variation of compartment pressures, temperatures, mass and energy inventories, heat structure temperature distributions, and energy exchange with adjacent compartments. The program is capable of describing the effects of leakage on containment response. Models are provided for fan cooler and cooling spray engineered safety systems. One to four compartments can be modeled, and any compartment except the reactor system may have both a liquid pool region and an air-vapor atmosphere region above the pool. Each region is assumed to have a uniform temperature, but the temperatures of the two regions may be different. The user determines the compartments to be used, specifies input mass and energy additions, defines heat structure and leakage systems, and prescribes the time advancement and output control.CDC7600,CYBER176;IBM360; FORTRAN IV and COMPASS (CDC7600), FORTRAN IV and BAL (IBM360); SCOPE 2.1 (CDC7600), OS/MVT (IBM360); 58K (octal) bytes and a CalComp or microfilm plotter (CONTEMPT-LT/028); 430K bytes and a CalComp or SC4060 plotter for graphical output (CONTEMPT-LT/026).
- OSTI ID:
- 6343262
- Report Number(s):
- ANL/NESC-433; ON: DE83048433
- Resource Relation:
- Other Information: Maxima of - 20 heat conducting structures 101 mesh points for each structure 20 regions for each structure 50 flow elements in one segment of the horizontal vent pressure suppression system 10 horizontal vents (or branches) in a segment 50 reductions within an input time-step CONTEMPT-LT can be used for analyzing the transient containment behavior of boiling-water reactors (BWRs) including Mark I, Mark II, and Mark III systems; pressurized-water reactors (PWRs), and experimental water reactor simulators or related experiments
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPUTER CODES
C CODES
LOSS OF COOLANT
THERMODYNAMICS
ACCIDENTS
BWR TYPE REACTORS
CONTAINMENT
HEAT TRANSFER
TEMPERATURE DISTRIBUTION
WATER
ENERGY TRANSFER
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220200* - Nuclear Reactor Technology- Components & Accessories