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The Analysis of TBP Process Streams for Calcium with the Flame Photometer

Description: Summary: A method was found for determining calcium concentrations in TBP process streams in spite of serious interferences bysodium, ferrous, uranyl, sulfate, phosphate, and sulfamate ions as well as by TBP. The precision attainable varied from sample to sample, depending upon its composition. In general, errors of 20% or greater occurred. The smallest determinable amount of calcium was about 10 mg/1.
Date: February 20, 1953
Creator: Brite, D. W.
Partner: UNT Libraries Government Documents Department
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Analytical procedures for the metal fabrication process

Description: From introduction: The present report describes further refinements of the apparatus and the method to meet a need for a sensitive determination of carbon in plutonium.
Date: February 20, 1951
Creator: Leboeuf, M. B.
Partner: UNT Libraries Government Documents Department
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Chemical Reactivity of Uranium Monocarbide and Uranium Mononitride with Water at 100°C.

Description: The monocarbide and the mononitride of uranium are potentially useful ceramic nuclear fuel materials. This paper reports the results of exploratory investigations of the reactions of uranium monocarbide and uranium mononitride with boiling water. Uranium dioxide, chemically stable in deoxygenated boiling water, was used as a control.
Date: February 26, 1959
Creator: Newkirk, H. W.
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.
Partner: UNT Libraries Government Documents Department
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Concentration and Final Purification of Neptunium by Anion Exchange

Description: It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless s… more
Date: February 10, 1959
Creator: Ryan, J.L.
Partner: UNT Libraries Government Documents Department
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Correlation of Chemical Analyses on Graphite Bars and Test Pile Results

Description: From abstract: "The chemical analyses of graphite test bars obtained from National Carbon Company and the analyses performed by the Hanford Works Laboratories Division do not correlate significantly with the test pile results, nor do the chemical analyses obtained from National Carbon Company agree with those done in the Handford Works Laboratories. Chemical results obtained at Hanford on samples taken lengthwise from individual bars correlated significantly with the individual test pile result… more
Date: February 5, 1948
Creator: Lane, J. J.
Partner: UNT Libraries Government Documents Department
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Corrosion Tests on Tantalum, Hastelloy C and Duriron in 234-5 Project Solutions

Description: Introduction: "Room temperature and elevated temperature, static immersion and vapor suspicion, corrosion tests were conducted with Duriron, Hastelloy C, and tantalum in hydriotic acid and 234-5 project process supernatant solution (synthetic environments. The data relevant to these tests are contained herein."
Date: February 25, 1949
Creator: Work, J. B. & Koenig, W. W.
Partner: UNT Libraries Government Documents Department
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Critical Mass Studies of Plutonium Solutions

Description: Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
Partner: UNT Libraries Government Documents Department
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Decontamination of Dissolver Vent Gases at Hanford

Description: The preceding report follows an extensive study made at Hanford of methods and equipment to remove effectively the dissolver vent gases.
Date: February 16, 1951
Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.
Partner: UNT Libraries Government Documents Department
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Detailed Procedure for K Reactors Rear ace Decontamination by Chemical Flush or the Rear Crossheaders, Pigtails and Nozzles as Authorized by the Production Test Authorization IP-239-N.

Description: The purpose of this procedure is to present a detailed, chronological presentation of the preliminary decontamination and post decontamination steps necessary to fulfill the requirements of the Production Test Authorization IP-239-N. The procedure attempts to present the required operation in sufficient detail to successfully accomplish the intent of the test. Certain procedures involve operations of a standard nature and have not been elaborated upon to any great extent, as it is expected tha… more
Date: February 25, 1959
Creator: Crossman, W.A.
Partner: UNT Libraries Government Documents Department
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The Determination of Total Plutonium in the Presence of Aluminum

Description: Introduction: "The adoption of aluminum nitrate as salting agent in the Redox process made it imperative that a method be available for determining plutonium in the presence of aluminum. However, large amounts of aluminum have been found to interfere with the determination of plutonium by the lanthanum fluoride procedure. Previous attempts to increase the accuracy of the lanthanum fluoride method, by precipitating LaF3 from 4 M HF (rather than 2 M), have been successful only when the initial pl… more
Date: February 10, 1950
Creator: Burns, R. E. & Barton, G. B.
Partner: UNT Libraries Government Documents Department
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Development of a Welding Process for End Closures on NPR and KER Fuel Element

Description: With the development of the zircaloy-2 clad uranium fuel element, it was necessary to develop a method of closing the end of the element after the extruded tubes were cut to the desired length. Regardless of the ultimate design of the closure, a satisfactory zircaloy-2 fusion welding technique had to be worked out. The first fully successful welding was performed with electron beam welding in a vacuum chamber. To make satisfactory welds, the electron beam welding involved time and equipment, pl… more
Date: February 22, 1960
Creator: Corey, T. B.; DeWitt, D. E. & Nelson, I. V.
Partner: UNT Libraries Government Documents Department
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Diameter Measurements of Slugs Before and After Prolonged Heat Treatment

Description: Abstract: "Diameter measurements of 25 slugs taken before and after a prolonged heat treatment showed no evidence of differences that would indicate blistering. The average effects of the treatment was different for the various slugs. Large differences in diameter measurements between slugs. Large differences in diameter between slugs and significant differences between indices and positions were found."
Date: February 16, 1948
Creator: Bennett, Carl A. & Lane, J. J.
Partner: UNT Libraries Government Documents Department
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Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959

Description: Operating plant experiences in restoring to useful service failed equipment contaminated through exposures to radioactive processes is of international interest to the nuclear industry. In accordance with a request from the Hanford Operations Office of the United States Atomic Energy Commission this report of the various measures taken in rehabilitating for re-use expensive engineered equipment has been compiled by the General Electric Company. This report is a review and summary of the dispos… more
Date: February 12, 1960
Creator: Kingsley, P. S.
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.
Partner: UNT Libraries Government Documents Department
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Elastic Analysis of Stress Conditions in a Reduction Bomb (Task III Replacement Pressure Vessel Model-1302)

Description: Several failures have occurred in reduction bombs used in metal production operations. A test program is being initiated to evaluate new metals for the construction of the bomb. In the test program, a tensile specimen is cycled through temperatures simulating operating temperatures, and the time to rupture is recorded in order to estimate the life in operation of a reduction bomb made with the candidate metal. In order to find the worst stress condition, the compressive, hoop, and bending st… more
Date: February 19, 1954
Creator: Merckx, K. R.
Partner: UNT Libraries Government Documents Department
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Evaluation of Fretting Corrosion of ZR-2

Description: Although the corrosion of resistance of Zircaloy--2 clad fuel elements in high temperature water is excellent, some concern has been expressed in regard to the resistance against fretting corrosion. Since this form of corrosion can proceed quite rapidly it could induce fuel element failure through penetration of the cladding. Fretting corrosion if it occurred, would take place either where the fuel element contacted the process tube or where portions of the fuel element contacted each other, e.… more
Date: February 5, 1960
Creator: Lobsinger, R. J.
Partner: UNT Libraries Government Documents Department
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Examination of Donut on Rupture Slug No. 14

Description: Pursuant to Dr. Kingdon's request for specific information concerning the donut pictured on pages 26-29 of WAPD-64, a close examination of this defect on Failure No. 14 was made. The slug was examined through 10 inches of Pb-glass and photographs were made. A clay impression of the surface area containing the donut was obtained, and using this impression, an Armstrong's Adhesive replica of this can wall surface area was cast.
Date: February 19, 1957
Creator: O'Keefe, D. P.
Partner: UNT Libraries Government Documents Department
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Flow Decay After an Electrical Power Outage in the PRTR

Description: Previously, W. S. Figg and T. W. Ambrose (HW-51767 Rev) have investigated the problem of flow decay following electrical power loss to the PRTR primary coolant pumps. However, since the time of their study many reactor piping changes have been made in the design; therefore, it has become advisable to re-examine the problem incorporating these changes.
Date: February 6, 1959
Creator: Muraoka, J.
Partner: UNT Libraries Government Documents Department
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The formation of chemical film deposits on aluminum surfaces

Description: From abstract: "The purpose of this investigation was to establish basic rates of formation of chemical films deposited on aluminum surfaces from water flowing over such surfaces. It was desired to obtain specific information, within certain ranges, as to the influence of temperature, water velocity, and type of aluminum on the rate of film formation."
Date: February 1952
Creator: Andrews, R. V.
Partner: UNT Libraries Government Documents Department
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