BEACON/MOD3; containment system fluid flow. [CDC CYBER176; CDC7600; FORTRAN IV (98%) and COMPASS (2%)]
The BEACON series of programs is designed to perform a best-estimate analysis of the flow of a mixture of air, water, and steam in a nuclear reactor containment system under loss-of-coolant accident conditions. The code can simulate two-component, two-phase fluid flow in complex geometries using a combination of two-dimensional, one-dimensional, and lumped-parameter representations for the various parts of the system. BEACON/MOD3 contains mass and heat transfer models for wall film and for wall conduction, and is suitable for the evaluation of short-term transients in PWR dry containment systems. The capability to examine the details of a two-component, two-phase flow field in one or two dimensions under nonhomogeneous, nonequilibrium conditions (unequal velocities, unequal temperatures between the two phases) allows analysis of such problems as the calculation of jet impact forces of a fluid leaving a pipe break, the motion of a large pressure wave across a compartment, the variation in flow properties as air is displaced from a compartment by steam and water, the water entrainment or deentrainment by a high-speed vapor flow, the flow of a flashing liquid, and many other complex nonequilibrium problems of containment system analyses.CDC CYBER176;CDC7600; FORTRAN IV (98%) and COMPASS (2%); NOS/BE (CDC CYBER176), SCOPE 2.1 (CDC7600); 120,000 (octal) words of SCM and 34,000 (octal) words of LCM for the largest of the eight sample problems. The LCM required is a function of the program size (i.e., the number of nodes or computational cells) and is dynamically allocated by the BEACON code.
- Research Organization:
- Argonne National Lab., IL (USA)
- OSTI ID:
- 6342602
- Report Number(s):
- ANL/NESC-767; ON: DE83048767
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP5/MOD1/018; LWR loss of coolant analysis. [CDC CYBER176; CDC7600; FORTRAN IV (90%) and COMPASS (10%)]
CONTEMPT-LT/028; CONTEMPT-LT/026; pressure-temperature response. [CDC7600,CYBER176; IBM360; FORTRAN IV and COMPASS (CDC7600), FORTRAN IV and BAL (IBM360)]
Related Subjects
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
B CODES
CDC COMPUTERS
COMPUTER CODES
COMPUTERS
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FORTRAN
HYDROGEN COMPOUNDS
LOSS OF COOLANT
ONE-DIMENSIONAL CALCULATIONS
OXYGEN COMPOUNDS
PROGRAMMING LANGUAGES
REACTOR ACCIDENTS
STEAM
THERMODYNAMICS
TRANSIENTS
TWO-DIMENSIONAL CALCULATIONS
TWO-PHASE FLOW
WATER