COBRA-NC: a thermal hydraulics code for transient analysis of nuclear reactor components. Volume 4. Users' manual for containment analysis

Technical Report · Fri Aug 01 00:00:00 EDT 1986

OSTI ID:5421482

Wheeler, C L; Thurgood, M J; Guidotti, T E; DeBellis, D E

COBRA-NC is a digital computer program written in FORTRAN IV that simulates the response of nuclear reactor components and systems to thermal-hydraulic transients. The code solves the multicomponent, compressible, three-dimensional, two-fluid, three-field equations for two-phase flow. The three velocity fields are the vapor/gas field, the continuous liquid field, and the liquid drop field. This volume of the manual provides the user with an explanation of the input required to simulate the response of multicompartment nuclear containment systems to postulated loss-of-coolant accidents that result in the release of steam, water, and/or noncondensable gases into the containment.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5421482
• Report Number(s): NUREG/CR-3262-Vol.4; PNL-5515-Vol.4; ON: TI86015600
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
HEAT TRANSFER
C CODES
HYDRAULICS
LOSS OF COOLANT
NUCLEAR POWER PLANTS
REACTOR COMPONENTS
TRANSIENTS
COMPUTERIZED SIMULATION
CONTAINMENT SYSTEMS
FORTRAN
MATHEMATICAL MODELS
TWO-PHASE FLOW
ACCIDENTS
COMPUTER CODES
CONTAINMENT
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
PROGRAMMING LANGUAGES
REACTOR ACCIDENTS
SIMULATION
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety