Development and Application of Computer Codes for Multidimensional Thermalhydraulic Analysis of Nuclear Reactor Components

Abstract

Components of reactor systems and related equipment are identified in which multidimensional computational thermalhydraulics can be used to advantage to assess and improve design, Models of single- and two-phase flow are reviewed, and the governing equations for multidimensional analysis are discussed, Suitable computational algorithms are introduced, and sample results from the application of particular multidimensional computer codes are given.