September 15, 1998
The Transient Reactor Analysis Code, TRAC, is used primarily to provide best-estimate simulations of real and postulated transients in nuclear reactors and related thermal-hydraulic facilities.
It features a two-fluid, 1D and/or 3D treatment for the thermal-hydraulics, together with other modeling capabilities necessary to describe a reactor system. It was originally developed in the 70's at Los Alamos National Laboratory, and is currently in the midst of an extensive modernization effort which involves in part a reimplementation of the code in Fortran 90.
A short note titled Benchmarks of Four Data Structure Options for TRAC-M, written in support of the modernization effort, is available here in HTML, gzipped PostScript (0.05 MB), or PostScript (0.3 MB).
The source code, as well as a GNU makefile which can be used to build an executable on a variety of platforms, is also available.
The code available above is an outgrowth of a related test code obtained from John Mahaffy. Four versions of that original code, which represent various evolutionary stages of the test code, are available here. Though none of the code below actually ended up in the above code, it was certainly a useful starting point. Details of changes made between versions are contained in the comments at the top of each file.