
doi: 10.2172/6240749
The BEACON code is a Best Estimate Advanced Containment code which being developed by EG and G, Idaho, Inc., at the Idaho National Engineering Laboratory. The program 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. The current version of BEACON, which is designated BEACON/MOD2A, contains mass and heat transfer models for wall film and for wall conduction. It is suitable for the evaluation of short term transients in PWR dry containment systems. This manual describes the models employed in BEACON/MOD2A and specifies code implementation requirements. It provides application information for input data preparation and for output data interpretation.
Loss Of Coolant, Nonbreeding, Nonboiling Water Cooled, Two-Phase Flow, 21 Specific Nuclear Reactors And Associated Plants, Reactor Accidents, B Codes, Fluid Flow, Light-Water Moderated, Reactor Safety, 22 General Studies Of Nuclear Reactors, Computer Codes, Pwr Type Reactors, Containment, Heat Transfer, Reactors, Engineered Safety Systems, Energy Transfer, Accidents, Containment Systems, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
Loss Of Coolant, Nonbreeding, Nonboiling Water Cooled, Two-Phase Flow, 21 Specific Nuclear Reactors And Associated Plants, Reactor Accidents, B Codes, Fluid Flow, Light-Water Moderated, Reactor Safety, 22 General Studies Of Nuclear Reactors, Computer Codes, Pwr Type Reactors, Containment, Heat Transfer, Reactors, Engineered Safety Systems, Energy Transfer, Accidents, Containment Systems, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
| selected citations These citations are derived from selected sources. This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically). | 0 | |
| popularity This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network. | Average | |
| influence This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically). | Average | |
| impulse This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network. | Average |
