The experimental data presented in HDC-1255 for the pressure drops through the various portions of a standard process tube assembly for isothermal flow are correlated in this report. Data include orifice sizes up to 0.310 inches. The equations have been adapted for the calculation of pressure drops or flow rates for clean tubes in pile operation. A systematic procedure is outlined for determining the pressure drops through each portion of the tube assembly. A method is presented for calculating the flow rate through a process tube from header pressure and panellit age readings.

This report details events of importance reported by the Hanford Operations Office for the week ending April 27, 1949.

This report details events of importance reported by the Hanford Operations Office for the week ending May 25, 1949.

The basis feed to the Redox plant is 5,000 lb/day of uranium, supplied both as current irradiated uranium metal slugs in jackets, and as uranium compounds from the existing metal waste storage tanks. The proportions of the two feeds are chosen according to the enrichment level of the irradiated metal, so as to give a plutonium production of about 650 gm/day. The design basis has been taken as 0 to 1,500 lb/day U from the waste storage system and 2,000--5,000 lb/day of irradiated metal. Only the feed preparation from irradiated metal is discussed in this process description, and a basis of 5,000 lb/day is used throughout. The metal feed has associated with it 172.5 lb. Al and 2.5 lb. Si as slug jackets, and contains about 650 gpm. plutonium and 3 {times} 10{sup 5} curies of gamma-emitting fission products (FP). The purpose of the feed preparation section is to remove the aluminum and silicon, and to dissolve the uranium as an aqueous solution for feed to the Redox extraction battery. Secondarily, it is tentatively proposed to provide equipment in this section to achieve a preliminary decontamination from ruthenium, which is poorly handled by the Redox extraction system, and from FP …

The overall testing of the vertical sheet rod system is a comprehensive program which has been divided into several phases. These phases are presented here, with a short resume of the testing required under each phase, to enable the formulation of the project proposal for the complete test program. It is intended that very detailed test requests will be issued for the separate phases as data from previous tests and further design studies indicate the exact information or data desired from a particular test.

This trip was spent in conferences with H. Etherington, A. Amroni, Geo. Anderson, and L.W. Fromm; and in inspection of components now being built for the Navy Test Rig which is to be installed at H Pile. Mr. Anderson believes that the entire assembly will arrive at Hanford between January 16 and 23, 1950. Much has yet to be designed and built, however. Also, certain incompatibilities with the H Pile were pointed out, and will be altered.

This paper describes a means of determining tritium oxides in urine relying upon the production of acetylene from the active water with subsequent measurement of the ionization caused by the tritium beta particle.