COBRA-NC: a thermal hydraulics code for transient analysis of nuclear reactor components. Volume 2. COBRA-NC numerical solution methods
Technical Report
·
OSTI ID:5396848
The COBRA-NC computer program has been developed to predict the thermal-hydraulic response of nuclear reactor components to thermal-hydraulic transients. The code solves the multicomponent, compressible three-dimensional, two-fluid, three-field equations for two-phase flow. The three fields are the vapor field, the continuous liquid field, and the liquid drop field. The code has been used to model flow and heat transfer within the reactor core, the reactor vessel, the steam generators, and in the nuclear containment. This volume describes the finite-volume equations and the numerical solution methods used to solve these equations. It is directed toward the user who is interested in gaining a more complete understanding of the numerical methods used to obtain a solution to the hydrodynamic equations.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5396848
- Report Number(s):
- NUREG/CR-3262-Vol.2; PNL-5515-Vol.2; ON: TI86010442
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BOILERS
C CODES
COMPUTER CODES
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR VESSELS
STEAM GENERATORS
THERMAL POWER PLANTS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
TWO-PHASE FLOW
VAPOR GENERATORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BOILERS
C CODES
COMPUTER CODES
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR VESSELS
STEAM GENERATORS
THERMAL POWER PLANTS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
TWO-PHASE FLOW
VAPOR GENERATORS