Report documenting a geologic study of the San Rafael River Desert Mining District, including background describing the stratigraphy and geologic history, and the economic geology study containing more extensive descriptions of the area's mineralogy and uranium ores, including a description of mining and impacts.

The Dumbo space propulsion reactor design concept is described, and the theoretical principles upon which the design is based are developed.

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In this document it is proposed to describe the plant site and to outline the nature of the pile in order to show the specific design and layout requirements for the production of plutonium by nuclear synthesis. The selection of the plant site involved a number of special considerations. An essential requirement was a large dependable supply of relatively pure water that remains at a fairly low temperature throughout the year. A large source of power was required to circulate the tremendous quantities of water. The potential dangers connected with the high energies of the nuclear reaction and the formation of a large quantity of radioactive by- products required large distances between each operating section of the plant, and between the plant and main rail and highway routes. The plant site layout and reactor areas are discussed in the first part of the chapter, followed by a functional description of the more essential pile components. The chapter concludes with a discussion of reactor instrumentation. 24 figs., 2 tabs.

Laboratory experience on the precipitation of Pu(IV) oxalate is summarized. Filterable Pu(IV) oxalate with a cake density of 0.6 to 0.7 g Pu/cm/sup 3/ cake was precipitated from Redox PR solutions containing 10 to 200 g/l Pu and 2 to 6 M HNO/sub 3/. Filtration ease increased with strike temperature from 35 to 60/sup 0/C. Optimum conditions for pre-reduction of Pu(VI) to (IV), precipitation, digestion, filtration and washing were determined for 60 g/l Pu. Separation factors of 80, 40, 20, and 12 for Al, Cr, Fe, and U and decontamination factors of 1.2, 12, and 3 for Am, Ru, and Zr--Nb were obtained.

The immediate objective of the LASL nuclear propulsion (Rover) program is the development of a heat exchanger reactor system utilizing uranium-graphite fuel elements and ammonia propellant. This program is regarded as the first step in the development of nuclear propulsion systems for missiles. The major tasks of the program include the investigation of materials at high temperatures, development of fuel elements, investigation of basic reactor characteristics, investigation of engine control problems, detailed engine design and ground testing. The organization and scheduling of the initial development program have been worked out in some detail. Only rather general ideas exist concerning the projection of this work beyond 1958.

This progress report by the Atomic Energy Division of the Savannah River Plant covers: Reactor Technology; Separation Technology; Engineering Assistance; Health Physics; and General Laboratory Work.

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Production of Pu, UO{sub 3}, and Pu metal exceeded forecasts. The 2nd attempt at Purex to recover Zr-Nb resulted in about 1/3 recovery, contaminated with about 1% of the Ce. Palm losses to Purex U product were eliminated, and the Pu content was reduced 5 to 10{times}. Routing the dissolver rinses into 3WB concentrator resulted into improved rinsing efficiency. Unclarified feed was processed through Purex HA column. In a test for using B in Redox, the B was routed completely to the waste; it was not detectable in product streams beyond the first cycle. Almost 1000 g Palm was purified and converted to oxide. Ferrous ion catalyzed the reduction of Palm VI by hydrazine or semicarbazide. Coordination of E-metal and NPR reprocessing at Redox in multipurpose dissolver was studied. An interim fission product recovery program at Purex will be directed toward low-efficiency collection of Pm {sup 147}. Locations for critical incident alarms were selected. (DLC)

Fission product distribution, fission product activities, and decontamination factors are terms of general usage in the Chemical Development Section. Specific values for some of these terms have been based upon data procured several years ago. In many cases more accurate basic numbers are now available. This report sets forth in tabular form detailed information on fission product activities as a function of decay time for certain conditions. It attempts to quality the use of the theoretical curie as a unit of activity to a unit having a more direct practical significance, the ``countable curie.``

This report presents results radiation monitoring from the separations section department for December 1953. Information is presented concerning radioactive effluent releases, personnel contamination, and general radiation monitoring from the facilities.

This is the monthly report for the Hanford Laboratories Operation, April, 1959. Metallurgy, reactor fuels, chemistry, dosimetry, separation process, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

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Pu output from separations plant was less than scheduled, but year-to- date production exceeded commitment by 4%. The Palm recovery run in Purex was the most successful to date. UO{sub 3} production and shipments met schedule. Purex had two pump failures. When Purex 1WW was centrifuged and treated to recover Ce, most of it remained in the centrifugate; only 14% was recovered. The prototype Pu ozonator in Redox performed well. Test runs on an acid precycle flowsheet and a proposed internal recycle scheme for Palm recovery were initiated in Redox. Recuplex had a change in solvent extraction feed preparation, and an installation of a safe-geometry bottom section on the stripping column. Storage of Purex 1WW wastes was discussed in a meeting. Conversion of Rexuplex to a manufacturing facility was completed. Cost estimates were developed for several alternative Palmolive processing schemes. Process flow diagrams were completed for Sulfex decladding of Yankee elements and Zirflex decladding of Dresden elements.

The purpose of this manual is to present a Hazard Breakdown of all jobs normally encountered in the laboratory work of the three sections comprising the Analytic Section, Metallurgy and Control Division of the Technical Department. A Hazard Breakdown is a careful analysis of any job in which the source of possible dangers is clearly indicated for each particular step. The analysis is prepared by individuals who are thoroughly familiar with the specific job or procedure. It is felt that if the hazards herein outlined are recognized by the Laboratory personnel and the suggested safety cautions followed, the chance for injury will be minimized and the worker will become generally more safety conscious. The manual, which is prefaced by the general safety rules applying to all the laboratories, is divided into three main sections, one for each of the three sections into which the Laboratories Division is divided. These sections are as follows: Section 1 -- 200 Area Control; Section 2 -- 100 Area Control; Section 3 -- 300 Area Control, Essential Materials, and Methods Improvement.

Production of Pu from separations plants was only 58% of April commitment because of Purex difficulties. UO{sub 3} production, shipments met schedules. Pu shape production and shipments exceeded forecast by 14%. Purex HS column, repaired Oct 1958, developed another leak and was bypassed April 18, resulting in Pu and U that required reprocessing. A Palm recovery run at Purex with all- reducing flowsheet, resulted in 87% recovery and excellent decontamination of product. The prototype dual-pass silver reactor in Purex C-cell plugged with offgases. Processing of unclarified feed through Purex solvent extraction continued. Redox dissolver batch sizes for E-metal processing were increased from 1.75 to 2.0 tons. Testing of first extraction cycle acidic flowsheet at Redox continued, with Np losses to HAW being below detection limit. Ru in 1AFS stream increased 10-fold F.P. activity but was removed in acid deficient U cycles. A sulfamic acid process is being explored for dissolving Pu metal. Scope design of Redox dissolver and RMA line replacement at Z plant was completed. Shielding effectiveness of medium and high density x-ray lead glass was compared.

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This report addresses the summary report of the Chemical Engineering Division.