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Records of Wells and Test Holes Drilled at the Nevada Test Site and Vicinity Since 1960

Description: From introduction: "This report was compiled to bring together the well data collected by the U.S. Geological Survey since 1960. This compilation includes data on 63 wells and test holes which were drilled since the Moore reports were prepared, or which were deepened or otherwise modified since 1960."
Date: April 21, 1965
Creator: Young, Richard A.
Partner: UNT Libraries Government Documents Department
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Status of plant assistance irradiations as of April 9, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of material undergoing irradiation awaiting dispositions material shipped during the months and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, ``Status Report Equations.`` The integrated exposure reported is the average exposure received by the surrounding uranium columns. Conversion to exposure received by the sample is left to the customer.
Date: April 23, 1965
Creator: Ferguson, J. H.
Partner: UNT Libraries Government Documents Department
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Status of special reactor process tube loadings, April 1, 1965

Description: This report provides the status of production test control tube loadings in reactor process tubes containing significant amounts of stainless steel (SS) materials.
Date: April 9, 1965
Creator: Bown, R. W.
Partner: UNT Libraries Government Documents Department
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Preliminary investigation of water coagulation characteristics as affects reactor effluent radionuclides

Description: Several theories have been advanced regarding the structure and characteristics of the aluminum hydroxide molecule when produced from alum in the water treatment process. The Water Treatment Task Force initiated this test to exploit a theory that increased adsorption of soil-leached elements, present in Columbia River water, by the floc particle would occur when the precipitate vas formed in its terminal pH state. This report discusses a half-plant test which was initiated at E Reactor Plant wherein the total sulfuric acid for pH correction was added with the alum to evaluate its affect on reactor effluent radionuclides.
Date: April 15, 1965
Creator: Frymier, J. W.
Partner: UNT Libraries Government Documents Department
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M-1 N-Reactor fuel development. Excerpts from N-Reactor Department Research and Development Budget for FY-1967 and Revision of Budget for FY-1966

Description: The use of metallic uranium fuel elements on a large scale in a pressurized water cooled graphite moderated power reactor environment in N-Reactor not only represents an extrapolation from previous Hanford fuel technology but it represents the only production-scale application of this concept in this country or abroad. Provision of a supporting technology is and will continue to be a major activity at Hanford as only a limited amount of directly applicable R&D will be available from other sites. The major benefit to be achieved through an extensive and continuing fuel program is attainment of the full capabilities of the N-Reactor at much reduced fuel cycle costs. The current N-Reactor fuel design represents the best engineering judgment of what is required for adequate performance. While the design is intentionally conservative, some features may not fully provide the level of performance required to sustain efficient reactor operation. Results of production-scale irradiation experience and special test irradiations will provide direction to a continuing program to correct any excesses or deficiencies in the initial fuel design. Reduction of unwarranted conservatism in the design will lower fuel fabrication costs, and correction of deficiencies will lower irradiation costs through increased time operated efficiency. Costs of this program are summarized for 1965, 66, and 67. The paper describes the scope of the program, its relationship to other programs, and technical progress in FY-1965 which included improved performance of the fuel elements even with the large number of rapid shutdowns of the reactor.
Date: April 19, 1965
Partner: UNT Libraries Government Documents Department
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C-1 coproduct development for N Reactor: Excerpts from N-Reactor Department research and development budget for FY-1967 and revision of budget for FY-1966

Description: This report discusses the production of weapon grade plutonium and tritium as an economically attractive mode of operation for N-Reactor. With the successful completion of the proposed research and development program coproduct production in N-Reactor could begin in January 1967. Approximately 5 kg of tritium could be produced at a reduction in unit total cost of up to $7 per gram equivalent when compared to other modes of operation of N-Reactor that yield only-weapon grade plutonium. Achieving this production level and unit cost requires a fuel and target design that will subject the materials to more severe temperature and exposure conditions than for the tube-in-tube design. Analyses of existing knowledge and experimental results obtained to date are very encouraging. However, there is a continuing need for additional experimental verification of the limiting conditions for both fuel and target to permit the specification of a production fuel and target design. The incremental cost of this program is estimated to be $1,055 million in FY-1965, $0.796 million in FY-1966 and $0.450 million in FY-1967 for a total of $2.3 million. The principal benefits to be derived from this expenditure of research and development funds are lower unit grade plutonium. When the reactor reaches equilibrium operation as a costs for both tritium and weapon dual-purpose reactor producing process steam for credit, it will be a highly competitive producer of plutonium and tritium in the AEC complex.
Date: April 19, 1965
Partner: UNT Libraries Government Documents Department
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Report to the Working Committee from Hanford

Description: This report to the working committee details technical activities and research programs for current reactor fuels, N-Reactor fuels, and reactor fuel development.
Date: April 12, 1965
Creator: Lewis, M.; Minor, J. E. & Stringer, J. T.
Partner: UNT Libraries Government Documents Department
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Letter: R. E. Skavdahl from S. M. Graves

Description: The purpose of this memorandum is to firm up requests for uranium oxide fuel elements. This first priority is to have two fuel columns fabricated for irradiation testing.
Date: April 23, 1965
Creator: Graves, S. M.
Partner: UNT Libraries Government Documents Department
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Iron-masonite shield attenuation effectiveness status report

Description: This is the fifth in a series of reports presenting the status and deterioration rates of the B. D, DR, F, and H biological shields. The last previous reports covering the period 1959 through March 31, 1961, indicated no significant decreasing trends in the attenuating effectiveness of the biological (iron-masonite) shields. At that time the combination of increasing average helium percentages and adding fringe poison in the smaller reactors resulted in corresponding reductions in shield temperatures below previous levels. Since then, there has been both an increase in reactor power levels and a greater emphasis on reduction of helium usage. Consequently, to limit biological shield temperatures and reduce the shield leakage, additional fringe poison has been employed for shield protection. This report covers the period from late 1960 through January 1, 1964.
Date: April 15, 1965
Creator: Gross, P. D.
Partner: UNT Libraries Government Documents Department
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Battelle-Northwest Monthly Activities Report, March 1965

Description: This report covers progress in the following areas: production reactor support; plutonium recycle program; PRTR HPD core; corrosion and water quality; PRTR pressure tubes; reactor components development; plutonium ceramics research; ceramics (uranium) fuel research; swelling studies; irradiation damage to reactor materials; ATR gas loop studies; graphite studies; metallic fuel development; plutonium and U-233 fueling of a fast compact reactor; FFTF studies; radiation effects on metals; customer work (support of HTLTR and EBWR); physics and instruments; chemistry; biology; radiation protection; and technical and other services.
Date: April 15, 1965
Partner: UNT Libraries Government Documents Department
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Monthly record report -- March 1965 research and engineering operation irradiation processing department

Description: This report covers progress in the following areas: process and reactor development; process technology; operational physics; and testing. Process and reactor developments covers reactor fuels, reactor engineering and radiological engineering. Process technology includes process standards, process change authorizations, and process standard relaxation. Operational physics includes updates on the B, C, D, F, H, KE, and KW reactors along with summaries of studies on reactivity and control and production related studies. Testing includes plant assistance; IPD and testing and irradiation services; other departments and contractors.
Date: April 5, 1965
Creator: Greager, O. H.
Partner: UNT Libraries Government Documents Department
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Hanford contribution for the twentieth high temperature fuels committee meeting, May 18--20, 1965: NMPO, Cincinnati, Ohio

Description: This report details post-irradiation annealing studies at 610 and 630 C which have shown that a submicron dispersion of UC in uranium is effective in reducing mobility of fission gases in uranium irradiated to 1.4 {times} 10{sup 20} fissions/cc (0.3 percent burnup). Electron microscopy of both the as-irradiated and the annealed samples show that a large population of less than 0.1{mu} UC particles develops which is believed to be responsible for the decreased swelling during annealing. Uranium fuel elements containing 390 ppm Fe and 840 ppm aluminum shows substantially less swelling both during irradiation and during post-irradiation annealing than uranium containing 140 ppm Fe and 120 ppm Si. Zircaloy-2 clad thorium-uranium fuel continues to show excellent performance in a pressurized water loop. Fuel swelling is currently 1.0 percent at an exposure of 3.7 {times} 10{sup 20} fissions/cc (11,000 MWD/T).
Date: April 26, 1965
Creator: Last, G. A.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, March 1965

Description: This report, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.
Date: April 22, 1965
Partner: UNT Libraries Government Documents Department
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Budget for FY 1967 and revised budget for FY 1966, Separations Research and Development Program (02 50 10 15 1)

Description: The Separations Research and Development Program consists of five identifiable activities in four general areas of effort. The five activities are: Chemical processes (Current processes and Innovations and new business); Chemical safety; Process equipment and control (equipment and instrument development); and By-products (recovery and purification). The proposed levels of funding for each of the five activities are listed. For each activity, the major accomplishments of the last year are listed, together with the proposed goals for the next two years. Significant trends in the program are noted.
Date: April 1, 1965
Creator: Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department
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Snow and rain washout coefficients for inorganic iodine vapor

Description: Washout coefficients for gaseous iodine in snowfall and an estimate of the coefficient for rainfall have been experimentally determined for the first time. The coefficient for rain is in agreement with theory. The coefficient for snow appears to depend upon crystal type and size as well as upon snowfall rate.
Date: April 16, 1965
Creator: Englemann, R. J. & Perkins, R. W.
Partner: UNT Libraries Government Documents Department
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Geologic Map of the Quartet Dome Quadrangle, Nye County, Nevada

Description: The following report provides a geological map of the Quartet Dome quadrangle in Nye county, Nevada.
Date: April 16, 1965
Creator: Sargent, K. A.; Luft, S. J.; Gibbons, A. B. & Hoover, D. L.
Partner: UNT Libraries Government Documents Department
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