From abstract: "The study evaluates the utilization of superheat and moisture separation techniques in the SM-2 design to improve the steam plant reliability and thermal efficiency. Ease of packaging, steam plant transient response, and capital costs are also considered. The reference design used for comparison is the steam cycle employing saturated steam at 600 psia described in APAE No. 40, Volume II."

Cutoff energies were calculated for height/diameter (H/D) values of 1, 3, 6, and 11.25 for cadmium cylinders. These are presented along with the values for H/D = 2 for comparison. Similar values for boron filters for H/D values of 1 and 2 are shown. (M.C.G.)

Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.

A brief series of experiments was performed to study the high temperature reaction of the Zircaloy-uranium-aluminum system at the request of Reactor Engineering Operation, Irradiation Processing Department. Knowledge of the high temperature behavior of this combination of materials is important to the evaluation of reactor behavior during possible accidental over-heating of a fuel channel.

A resume of Health Physics activities for January, February, and March, 1960 is presented. Discussions and tabulations which summarize results of field surveys, bioassay, personnel monitoring, and environmental surveys are included.