A program is given to calculate the critical size and the two-group flux distributions in a cylindrical reactor with identical top and bottom reflectors. The core is not reflected on the sides. In addition to the size and the flux distributions, the program output included the initial fuel investment together with parameters which will enable evaluation of the fission heat release distribution. The output of a parameter to enable the manual calculation of coolant outlet temperature from a gas cooled reactor is also available. The program may be used for reflector savings studies, for heat distribution calculations, or as a check program for more ambitious calculations. (auth)
U.S. Atomic Energy Commission depository collection.
Note
NSA number: NSA-17-031668 OSTI Identifier 4668150 Research organization: Australia. Atomic Energy Commission Research Establishment, Lucas Heights, New South Wales.