A proposal by ``S`` Division that operations be simplified by adding fixed amounts of calcium and iodine in the reduction step as a time saving device has been investigated. Ten test runs in the 410--430 gram range have been compared with twenty normal runs made in this period. The average yields were 98.27% for the normal method and 98.26% for the test runs. No effect on individual yields by the variance in percent calcium and the iodine ratio was observed. Seventy percent of the runs normally fall into the 410--430 gram range. By controlled compositing of the feed batches, it should be possible to increase the percentage of the PuF{sub 4} runs that fall in this range.

A study has been made of the elution behavior of curium(III), americium(III), plutonium(III), actinium(III), plutonium(IV), neptunium(IV), uraniuM(IV), thorium(IV), neptunium(V), plutonium (VI), uranium (VI), lanthanum(III), cerium(III), europium(III), ytterbium(III), ytterium(III), strontium(II), barium(II), radium(II), cesium(I) with 3.2 M, 6.2 M, 9.3 M, and 12.2 M HCl solutions from Dowex-50 cation exchange resin columns. These elutions show that in high concentrations of hydrochloric acid the actinides form complex ions with chloride ion to a much greater extent than the lanthanides. The strengths of the tripositive actinide complex ions apparently go in the order plutonium > americium> curium, although their ionic radii also decrease in this same order. To explain these results, a partial covalent character may be ascribed to the bonding in the transuranium complex ions. It is shown that a reasonable structure for such covalent bonding involves hybridization of the 5f orbitals in the actinide elements.

The fission and spallation reactions caused in uranium by bombardment with high energy protons (340 t o 350 MeV) were investigated. The reaction products were separated from the target by chemical processes and identified by their radioactive properties. The relative yields of the observed fission products were measured, and the results plotted as a function of mass number. Several of the spallation products were identified and their yields estimated. An attempt was made to determine the most probable atomic number for a nuclide of given mass formed directly from fission. Studies were made of the relative yields along several isobaric chains as a function of atomic number. From these data predictions of the mass and charge of the fissioning nucleus are made.

None

Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentration step has been modified to permit the greater capacity. At 600 MWD/T (522 g/t) then, the 112 tons uranium per month capacity limits the plutonium output of the plant to 58.5 Kg per month at 80% operating efficiency. The remaining 38 Kg plutonium per month may be processed in the B and T BiPO{sub 4} plants at an operating efficiency of 89.5%; if this operating efficiency cannot be realized, the postulated production rate may be met by either an increased Redox efficiency or by accepting an increased plutonium waste loss of 1% on some portion of the BiPO{sub 4} production.

None

The slow neutron transmission of several samples of plutonium is being investigated with the Columbia Neutron Velocity Spectrometer. The spectrometer, which has been described previously (Rainwater et al., Phys. Rev. 71, 65 (1947)), was recently improved, recalibrated, and the operational factor reevaluated (CUD-59). Results reported here were obtained by the procedure described in that report.

None

None

This report discusses the feasibility of designing and building two 100 Areas at the Coyote Rapids site on the Columbia River. It incorporates the individual studies prepared by the Power and Mechanical Division-HDC-2241, Reactor Division-HDC-2239, Project Engineering Division-HDC-2244, Principal Engineer and HDC-2242, and the Engineering and Construction Services Division-HDC-2243, each outlining the proposed course of action and requirements for that facet of the contemplated work in which they are primarily interested.

As originally installed, the primary process pump turbines in 190-B were arranged to accelerate considerably upon loss of BPA electric power supply to the Process Pump House. However, the acceleration comes too late to be of value in maintaining top of riser pressure within the first second or two, and the acceleration results only in maintaining final process water pressure and flow at values higher than needed. It is desired to limit the acceleration of the turbines to a relatively small amount in order to decrease the emergency steam demands and keep the combined steam demands of 100-B and 100-C Areas within the capacity of 184-B Boiler House, as outlined in Document HDC-2106, revised June 4, 1951. This report recommends that the desired results be obtained by simply reducing the speed setting of the turbine speed governors. No new equipment is needed. The setting of the emergency over speed trips would be left unchanged.