NUCLEAR ROCKETS

One of the most important factors in the development of nuclear rocket
engine designs is to be able to accurately predict temperatures and
pressures throughout a fission nuclear reactor core with axial hydrogen
flow through circular coolant passages. CAC, from NASA Lewis Research
Center, is an analytical prediction program to study the heat transfer and
fluid flow characteristics of a circular coolant passage. CAC predicts as
a function of time axial and radial fluid conditions, passage wall
temperatures, flow rates in each coolant passage, and approximate maximum
material temperatures.

Although CAC was originally developed in FORTRAN IV for use on an IBM 7094,
this version is written in ANSI standard FORTRAN 77 and is designed to be
machine independent. It has been successfully compiled on IBM PC series
and compatible computers running MS-DOS with Lahey F77L, a Sun4 series
computer running SunOS 4.1.1, and a VAX series computer running VMS 5.4-3.
CAC requires 300K of RAM under MS-DOS, 422K of RAM under SunOS, and 220K
of RAM under VMS. No sample executable is provided on the distribution
medium. Sample input and output data are included. The standard
distribution medium for this program is a 5.25 inch 360K MS-DOS format
diskette. CAC, LEW-15400, was developed in 1966, and this machine
independent version was released in 1992. Program $450; documentation
$36.

COSMIC
The University of Georgia
382 East Broad St, Athens, GA 30602-4272
706-542-3265,  FAX: 706-542-4807

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