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The TRAC-PF1/MOD1 Computer Code

  • Dennis R. Liles
  • John H. Mahaffey

Abstract

The Transient Reactor Analysis Code (TRAC) is an advanced best-estimate systems code for analyzing LWR accidents. It is being developed at the Los Alamos National Laboratory under the sponsorship of the Reactor Safety Research Division of the US Nuclear Regulatory Commission. A preliminary TRAC version consisting of only one-dimensional components was completed in December 1976. This version was not released publicly nor formally documented. However, it was used in the TRAC-P1 development and formed the basis for the one-dimensional loop component modules. The first publicly released version was TRAC-P1, completed in December 1977. It is described in the Los Alamos report LA-7279-MS.

Keywords

Countercurrent Flow Nuclear Regulatory Commission Light Water Reactor Pool Formation Accident Sequence 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • Dennis R. Liles
    • 1
  • John H. Mahaffey
    • 1
  1. 1.Safety Code Development Group, MS K553Los Alamos National LaboratoryLos AlamosUSA

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