CAC is analytical prediction program to study heat-transfer and fluid-flow characteristics of circular coolant passage. Predicts, as function of time, axial and radial fluid conditions, temperatures of passage walls, rates of flow in each coolant passage, and approximate maximum material temperatures. Written in ANSI standard FORTRAN 77.
Analyzing Flows In Rocket Nuclear Reactors
NASA Tech Briefs ; 18 , 3
1994-03-01
Miscellaneous
No indication
English
Analyzing Flows in Rocket Nuclear Reactors
Online Contents | 1994
Outlook for Nuclear Rocket Engine Reactors
Springer Verlag | 2012
|Coolant flows in prismatic fuel and particle bed nuclear reactors for rocket applications
American Institute of Physics | 1993
|Novel radiation calculations on rocket reactors
NTRS | 1962
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