Published January 1984 | Version v1
Report

TRAC code improvements

  • 1. Los Alamos National Lab., NM

Description

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. The first publicly released version was TRAC-P1, completed in December 1977. It is described in the Los Alamos report LA-7279-MS. The TRAC-P1 program was designed primarily for the analysis of large-break loss-of-coolant accidents (LOCAs) in pressurized water reactors (PWRs). Because of its versatility, however, it can be applied directly to many analyses ranging from blowdowns in simple pipes to integral LOCA tests in multiloop facilities. A refined version, called TRAC-P1A, was released to the National Energy Software Center (NESC) in March 1979. It is described in the Los Alamos report LA-7777-MS. TRAC-PD2 contains improved reflood and heat-transfer models and improvements in the numerical solution methods. TRAC-PF1 was designed to improve the ability of TRAC-PD2 to handle small-break LOCAs and other transients. TRAC-PF1/MOD1 was designed to provide full balance-of-plant modeling capabilities. Some distinguishing characteristics of TRAC-PF1/MOD1 are summarized

Additional details

Publishing Information

Imprint Title
Proceedings of the eleventh water reactor safety research information meeting. Volume 2
Journal Page Range
p. 200-206.
Report number
NUREG/CP--0048-Vol.2

Conference

Title
11. NRC water reactor safety research information meeting.
Dates
14-24 Oct 1983.
Place
Gaithersburg, MD (USA).