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.

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)

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.

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.

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.

This report addresses the chemical technology divisions' monthly report for chemical development.

This report discusses the interim program for the production of neptunium oxide at HAPO which applies the following processing steps: isolation of neptunium from the Purex process streams, using Purex flow sheets specially adapted for this purpose; purification of the neptunium nitrate by an ion exchange process carried out in one of the Redox laboratory (222-S) multi-curie cells; and precipitation of neptunium oxalate and conversion of the oxalate to oxide in laboratory-type equipment. The process, being still in the developmental stages, is as yet subject to extreme fluctuations, both conditions and results.

This report discusses risks associated with the underground storage of high-level radioactive wastes from the Purex Plant at Hanford in 1957. Radiation doses and contamination of the Columbia River resulting from storage tank leaks are discussed.

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This report addresses the AEC symposium on particle-fluid mechanics

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This study was undertaken to determine the most feasible and economical process or path for closing the uranium fuel cycle at HAPO, and to establish what benefits, other than improvement in FPD`s competitive position, would result from the selected closed fuel cycle. The study was separated into four phases; Phase I includes the selection and organization of plausible processes and the establishment of a realistic and effective evaluation procedure, Phase II will include evaluation and selection of an optimum path based on a medium range and a short range approach (5 to 10 years), Phase III will include evaluation and selection of an optimum path based on a long range approach (> 10 yrs.), and Phase IV will include refinement of previous work and issuance of a final report summarizing the study and the conclusions or recommendations which develop from the study. Phase I of the study has been completed. The purpose of this paper is to document the assembled data and the completed work.

The use of the porposed full reactor operational charge-discharge facilities will to some degree change the method of reactor operation from a ``batch`` to a ``continuous`` process. This change in the operational process will require modifications to coolant flow supply and monitoring equipment. Since a continuous and adequate coolant supply is essential to prevention of the release of fission products from the irradiated fuel elements this modification merits a hazards analysis.

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

The 107-B retention basin was constructed in 1943--44 as part of the original reactor installation. Thermal stressing has caused extensive cracking of the concrete walls and leaking at cracks and joints, requiring repeated maintenance including a major repair program in 1952--53. Although a major repair or replacement program will eventually be necessary, existing basin leakage does not require immediate action, other than periodic control effort, with one exception. Effluent from 107-B leakage is flowing into the 181-B river pumphouse forebay, measurably increasing the temperature of the raw water and raising the question of continued stability of the building foundation. A basic inadequacy also exists in the inability to dispose of undesirable effluents other than to the river. The unique situation of B Reactor adjacent to the C Reactor effluent system permits consideration of improving the effluent disposal situation in this one area with minimum capital investment. The purpose of this report is to provide the scope for a project proposal for interim effluent system modifications in 100-B Area only. This will avoid future production losses and improve effluent disposal capability during resolution of a more permanent solution to the overall problem of effluent routing and treatment.

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This document details activities of the irradiation processing department during the month of April, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and engineering operations; production and reactor operations; facilities engineering operation; employee relations operation; and financial operation.

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The development of a reduction step using plutonium trichloride instead of plutonium tetrafluoride in 234-5 Building processing was proposed early in 1958. This process change was intended to reduce the neutron radiation associated with plutonium fluoride. Neutron dose estimates shaw that over half of 234-5 Building neutron exposure is associated with the fluoride process steps. Other measurements show that a 60-fold reduction in neutron flux could be realized by converting to a chloride process. Progress up to September 1958, was described in a document covering the chemical aspects of the development work, including batch preparation of trichloride. The present report summarizes work done on this process over the past year, emphasizing continuous preparation of plutonium trichloride in large-scale equipment, the reduction of this product to metal, and large-scale recovery of slag and crucible.

This document details activities of the irradiation processing department during the month of September, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

This document details activities of the irradiation processing department during the month of October, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor operations; Facilities Engineering operation; Employee Relations Operation; and Financial operation.