CONTEMPT4/MOD6. PWR & BWR Containment Analysis
- Los Alamos National Lab., NM (United States)
CONTEMPT4/MOD6 describes the response of multicompartment containment systems subjected to postulated loss-of-coolant accident (LOCA) conditions. The program can accommodate both pressurized water reactor (PWR) and boiling water reactor (BWR) containment systems. Also, both design basis accident (DBA) and degraded core type LOCA conditions can be analyzed. The program calculates the time variation of compartment pressures, temperatures, and mass and energy inventories due to intercompartment mass and energy exchange taking into account user-supplied descriptions of compartments, intercompartment junction flow areas, LOCA source terms, and user-selected problem features. Analytical models available to describe containment systems include models for containment fans and pumps, cooling sprays, heat conducting structures, sump drains, PWR ice condensers, and BWR pressure suppression systems. CONTEMPT4/MOD6 also provides analytical models for hydrogen and carbon monoxide combustion within compartments and energy transfer due to gas radiation to accommodate degraded core type accidents.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Reactor Regulation
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 139263
- Report Number(s):
- ESTSC/NRC-000009CYYMP00; NESC-818
- Resource Relation:
- Other Information: PBD: 1 Mar 1986
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
22 NUCLEAR REACTOR TECHNOLOGY
C CODES
LOSS OF COOLANT
REACTOR ACCIDENTS
REACTOR SAFETY
PRESSURE DEPENDENCE
HEAT TRANSFER
TEMPERATURE DEPENDENCE
COMPUTER PROGRAM DOCUMENTATION
COMPUTERIZED SIMULATION
HYDRAULICS
MASS TRANSFER
SYSTEMS ANALYSIS
CONTAINMENT