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Analytical procedures for the plutonium Metal Fabrication Process

Description: A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.
Date: January 15, 1951
Creator: Kendall, L. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Research Section Progress Report for January 1950

Description: The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Clarification of Redox Feed (1AF) by Filtration : A Semi-Works Study Progress, Redox Technical Data Study No. 8

Description: The following report was made to determine the effective clarity improvement, flow rate characteristics, and operational problems encountered on passing Redox uranium feed solution through sintered, modified Type 304 stainless steel filter elements.
Date: October 15, 1948
Creator: Cooper, V. R. & Coleman, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comments on Engineering Review of PRTR by Atomic Power Equipment Department

Description: On a project of the magnitude and complexity of the Plutonium Recycle Test Reactor is was considered prudent engineering practice to obtain an independant design review by a competent off-site group that had not participated in any way in the development of the design. Accordingly, the Atomic Power Equipment Department of the General Electric Company was requested to make such an engineering review, and an Assistance to Hanford contract authorizing this work was approved by the Atomic Energy Co… more
Date: October 15, 1959
Creator: Reactor and Fuels Researcg and Development Operation Hanford Laboratories Operation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Construction Completion Report: CAI-816, 100-N Reactor Plant

Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of Stellite in Redox Streams

Description: The following report provides results from laboratory tests on the corrosion resistance of various types of stellite facings on astenitic stainless steel T-347 to Redox streams.
Date: May 15, 1950
Creator: Koenig, W. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Criteria for PRTR High Pressure Loop Project CAH-841

Description: The PRTR pressure loop is an experimental facility to be installed in the Plutonium Recycle Test Reactor, Building 309, for use in testing the feasibility of reactor cooling systems utilizing high pressure water or steam as the coolant. It will furnish operating experience with such systems and serve to test fuel elements and components designed to operate in such environments.
Date: October 15, 1959
Creator: Fox, J. C.; Jakub, M. T. & Kelly, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Americium

Description: The following report describes a successful procedure used for the determination of americium in the presence of plutonium. Provided are articles listed that describe the research done in developing the method.
Date: October 15, 1952
Creator: Schmidt, H. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report- August 1959

Description: Sinterability studies on mixtures of UO2 and PuO2 powders have been continued. All of the censities from previous sintering experiments have been recalculated utilizing a somewhat different water immersion technique. Since densities of pellete obtained by physical dimensions are inaccurate due to chipping, and water immersion does not account for the open porosity, the pellets were coated with clear krylon before being immersed in water. This effectively sealed the open pores. Plots of density … more
Date: September 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report- December 1958

Description: Two Zircaloy-clad capsules (GKH-14-19,20) containing two compacts each of high density PuO2-UO2 mixed crystal oxides were shipped to the MTR in December 2, 1958. The compacts contain 0.026 a/o PuO2, have densities of 91 percent of the theoretical value, and will generate the same specific power as an Al-1.8w/o Pu alloy rod of the same diameter would produce. Two capsules (GKH-14-21,22) have been prepared and contain three compacts each of low density, about 65 percent of the theoretical value, … more
Date: January 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report - February 1959

Description: Plutonium Oxide Fuels. Mixtures of PWR grade UO2 containing 10, 20, 30, 40, 50, and 60 w/o PuO2 were sintered in hydrogen for 44 hours at 1600 C to get additional data on solubility in this system. Densities of all the pieces were low, approximately 80 percent of theoretical; however, solid solution formation was complete in every case. The low density material should not affect lattice parameter values, but it did slightly reduce the intensity of the reflections.
Date: March 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report- March 1959

Description: Basic Studies. It has been reported previously that mixed crystals of PuO2 and UO2 have a higher sintering rate than UO2 alone. However, results to the contrary were obtained on addition to 1/4, 1/2, 1, 2, 5, and 10 w/o PuO2 to PWR grade UO2. Pellets of the above concentrations were heated for one hour in hydrogen at 100 C intervals from 1000 to 1600C.
Date: April 15, 1959
Creator: Hanford Laboratories Operation Fuels Preparation Department, Irradiation Processing Department
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report- May 19599

Description: Plutonium Fuels Development Basic studies. Experiments to determine the effect of plutonium dioxide additions on the sinterability of UO2 have continued. PuO2 has been added to ball milled PWR grade UO2 as a physical mixture, and in the form of the mixed crystal oxide.
Date: June 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Reports-June 1959

Description: Basic Studies. Sinterability experiments in the system UO2-PuO2 have continued, and data are available at one hour hold times across the UO2-PuO2 composition limits. Sintered densities appear to be markedly dependent on pressed densities with densification occurring very rapidly at higher pressing pressures. The following table illustrates the effect of one hour at temperature on final density for pure plutonium dioxide pressed to both 40 and 60 percent of theoretical density.
Date: July 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Furnance Pressures on Quality of Remelted Uranium : Final Report, Production Test 314-59-M

Description: The following report follows a test for remelting and casting uranium scrap specified that a pressure of 25 microns or less must be attained within the furnace before a charge is melted. The report was made to evaluate the effect of furnace pressures upon the quality if recast uranium metal.
Date: February 15, 1951
Creator: Kattner, W. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electroless Nickel Plating

Description: Summary: "This investigation showed that a sound , weather-resistant coating can be applied to uranium that the surface to be plated is cleaned and etched properly. Using the proposed two-bath plating method at 80 C., a four-mil nickel coat can be deposited in thirteen hours."
Date: November 15, 1950
Creator: Groot, C. & Hopkins, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Hanford Remote Pipetter

Description: The Hanford Remote Pipetter has developed into a very useful tool for routine pipetting by semi-skilled non-technical personnel. Radiation exposure to the operators has decreased to normal background levels as proper shielding exists between the sample and the operator. The results achieved by the pipetter have demonstrated its flexibility and simplicity of operation.
Date: January 15, 1954
Creator: Hammill, K. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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