Approach to Fluid-Mechanics Calculations on Serial and Parallel Computer Architectures (PWR; BWR; TRAC Code)

摘要

The Transient Reactor Analysis Code (TRAC) is a large FORTRAN thermal-hydraulics program designed to solve problems involving internal flows in nuclear reactors. The current versions have been designed for a CDC 7600 and CRAY 1 but benchmarks have been run in parallel simulations. This paper will discuss the methods in use, the reason that these techniques are effective, and their extension to parallel machines. (ERA citation 08:040930)