This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.

Information concerning the pressure-flow relations in reactor process tubes at very low heat generation rates is of value for determining flow requirements during shutdown conditions. Since such information is quite difficult to calculate when boiling occurs, a brief laboratory investigation was conducted to obtain experimental data. The data obtained for BDF geometry are recorded in this report for distribution to those persons having an interest in the application of the results to reactor operation.

On January 22, 1960, HW-63487 Piping Changes for Increased Production at B, D, DR, F, C, and R Reactors, was published. This study investigates the valve pit piping, front and rear face piping,and effluent lines between the 105 Buildings,and the retention basins to determine modifications necessary to increase power levels in the 100-B, D, DR, F, C, and H Areas by increasing either or both temperatures and flows. The study was based on detailed hydraulic and stress calculations of the existing and proposed piping systems which because of their detailed and voluminous nature were not included in the study. It is the purpose of this study to document, in so far as possible, these calculations together with pertinent information which was not included in the original study.

A preliminary report on the operations and procedures for handling a 125- w thermoelectric generator and its isotopic heat source is presented. Full-scale mock-ups were used to develop the procedures. A cylindrical metal block of Inconel X will be remotely loaded with an isotope at ORNL. The block will then be sealed snd loaded into a specially designed cask and shipped by rail to the Martin nuclear hot cell facility, where the second phase of the operation will be conducted. (W.D.M.)

The need for, and the adequacy of, the sodium carbonate washing technique in chemical purification of tributyl phosphate-hydrocarbon extractant prior to its re-use in radiochemical processing was examined, primarily in terms of Ru, Zr, and Nb activities. Operating experience from ORNL Purex and Thorex Pilot Plants is compared with Hanford operations and upper limits for activities are suggested. Recommendations are made for development studies with the ORNL Power Reactor Fuel Processing Pilot Plant. (W.D.M.)

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1959, activities, service, organizational leadership, and other information about scouting programs.