Approach to fluid-mechanics calculations on serial and parallel computer architectures. [PWR; BWR; TRAC code]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5936763

Liles, D R; Mahaffy, J H; Giguere, P T

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.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5936763
• Report Number(s): LA-UR-83-1881; CONF-830581-2; ON: DE83014143
• Resource Relation: Conference: Conference on large scale scientific computation, Madison, WI, USA, 16 May 1983
• Country of Publication: United States
• Language: English

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