UNT Libraries Government Documents Department - 151 Matching Results

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Absorption of Organic Acids on Thoria

Description: The adsorption of acetic and oleic acids on the surface of thoria was studied by means of infrared spectroscopy. An infrared analysis of the adsorbates before and after adsorption using differential double bean methods indicated that the adsorption of organic acids on thoria surfaces occurs by an esterification reaction between the organic acid and the hydroxylated thoria surface. Ammonia vapor will not adsorb on thoria, indicated the basic character of the hydroxylated surface.
Date: December 31, 1959
Creator: Bradford, Harold R. & Wadsworth, Milton E.
Item Type: Refine your search to only Report
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Analysis of Fuel Element Core Blanks for Argonne Low Power Reactor by Gamma Counting

Description: A technique based on a determinaiion of the differential counting rate exhibited by the 184-kev gamma radiation associated with the decay of U/sup 235/ was developed for the determination of the U/sup 235/ content in Argonne Low Power Reactor fuel element core blanks. The Argonne Low Power Reactor core blanks were an aluminum-highly enriched uranium alloy containing 17.5 weight per cent uranium (approximately 4 g U/sup 235/) having the following dimensions: length, 6.875 inches, width, 3.31 inc… more
Date: December 1, 1959
Creator: McGonnagle, W. J. & Perry, R. B.
Item Type: Refine your search to only Report
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Analysis of Radiation From Hnpf Cold Traps and Primary Sodium Pumps During Removal and Shipping

Description: The expected maximum contamination of the HNPF cold traps and primary sodium pumps was determined along with the maximum dose rates from these components during removal and shipping. Suitable shielding for casks to be used in the removal operation and for shipping these components away from the reactor site is specified. Access to an unshielded cold trap is limited by high dose rates, i.e., 100 mr/hr at 120 ft, after 180 days decay time. A handling cask providing a radial shield of 3 in. of lea… more
Date: December 15, 1959
Creator: Rhoades, W. A.
Item Type: Refine your search to only Report
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Annual Report of Research Progress

Description: This technical report constitutes a brief review of the work undertaken, entirely or in part, under the Contract AT(30-1)-1772 with eh United States Atomic Energy Commission. The work published during 1959 is listed at the end of this report and copies of the reprints or reports are attached where available. These investigations have been concerned with the examination of defect production and behavior as it may be observed by high frequency ultrasonic attenuation and velocity (modulus) changes… more
Date: December 31, 1959
Creator: Truell, Rohn, 1913-1968
Item Type: Refine your search to only Report
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Atmospheric Signals From Explosions and Their Interpretation

Description: Results are reported from a series of experimental highexplosive shots under inversion conditions at the Nevada Test Site which were made in an attempt to refine blast prediction techniques. Applications of the data in determinations of the amount of energy which remains in the blast wave as it reaches acoustic level and in determinations of the magnitude of the reflection factor when the blast wave strikes the ground are discussed. Data on shock wave propagation are presented graphically. It i… more
Date: December 1, 1959
Creator: Reed, J. W.
Item Type: Refine your search to only Report
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Attempted Modification of Susceptibility of Tumors to X-Radiation : Final Report for August 1 1957 to August 31, 1959

Description: Attempts to secure a high degree of synchronization of cell division of the Krebs mouse ascites carcinoma, by combined use of aminopterin and citrovorum factor, and by use of colchicine and N-acetyl colchinol, were unsuccessful. In the course of the work, a new method for securing smears of ascites tumor cells was out, which we believe will be found useful
Date: December 31, 1959
Creator: Beck, Lyle Vibert, 1906-
Item Type: Refine your search to only Report
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Autoclave Corrosion Behavior of U-Low Carbon and U-Low Zirconium Alloy Fuels

Description: A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.
Date: December 1, 1959
Creator: Goffard, J. W.
Item Type: Refine your search to only Report
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BIOLOGICAL AND MEDICAL RESEARCH DIVISION SEMI-ANNUAL REPORT FOR JULY THROUGH DECEMBER 1958

Description: Progress is reported in the following studies: the control of a scabies- like mange of rats and pinworms in mice; in vivo measurement of Sr/sup 90/ in dogs; the effects of the chronic ingestion of Sr/sup 90/ in mice; investigation of the tritium labeling of organic compounds by the self-irradiation method; the delayed effects of x irradiation in chickens; development of a new method for the assay of enzymatic activity of various homocysteine transmethylases; the use of a punched-card system for… more
Date: December 1, 1959
Item Type: Refine your search to only Report
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Casting and Fabrication of Core Material for Argonne Low Power Reactor Fuel Elements

Description: The manufacture of fuel blanks used in the fabrication of fuel elements for the Argonne Low Power Reactor is described. The thin, plate-type elements contain a wrought aluminum-base core alloy with a nominal composition of 17.5 wt.% enriched uranium, 2.0 wt.% nickel, and 0.5 wt.% iron, clad with an aluminum-- nickel alloy. The fuel ele ments were fabricated by a picture-frame technique, employing elemental silicon bonding and followed by hot and cold rolling to size. Development, casting, hot a… more
Date: December 1, 1959
Creator: Salley, R. L. & Burt, W. R., Jr.
Item Type: Refine your search to only Report
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Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Description: Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs. more
Date: December 1959
Creator: Salley, R. L. & Burt, W. R., Jr.
Item Type: Refine your search to only Report
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Charging and Discharge of Demineralizer Resins. Section IV. First Performance. Core I, Seed 1. Test Results DL-S-180, T-612085

Description: The purpose of the test was to determine if the 1A Canal Water System Demineralizers can be satisfactorily charged with resin. The 1A Canal Water System Demineralizer was satisfactorily charged with resin and conductivity of the demineralizer effluent was less than 0.1 microbes as specified in the Test Procedure.
Date: December 3, 1959
Creator: Eckenrode, G. E.
Item Type: Refine your search to only Report
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Chemical Processing Department monthly report, November 1959

Description: The November 1959 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)
Date: December 21, 1959
Item Type: Refine your search to only Report
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for August 1959

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed by taking a macro photograph of the desired gradient by monochromatic (436 m mu ) light transmitted by the solution normal to the gradient in an appropriate diffusion cell. Two Druhm runs were terminated due to malfunction of the sodium metering system and the third run was terminated when the UF/sub 6/ nozzle ruptured. Calculations of particle temperature versus time relations for the flame denitration-cal… more
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Item Type: Refine your search to only Report
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Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Item Type: Refine your search to only Report
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Condensate System. Section II. Fifth Core I, Seed 1. Test Results DL-S-105

Description: The purpose of the test was to fill the condensate storage tank and the Condensate System and obtain satisfactory preliminary operation. The components of the Condensate System performed adequately and satisfactorily with the exception of fill control valve (M9-VI). This valve (M9-VI) is not used in the current operation procedure.
Date: December 8, 1959
Item Type: Refine your search to only Report
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Continuity of Operations Program: Prime Separations and Uranium Conversion Facilities

Description: This Program detailed in this report is related to the Product Development, Palmolive, and Non-Production Fuels Programs under New and Special Products and Processes Category where the prime separations plants supply raw materials or processing support of these other programs. Likewise, Increased Plant Return Program items affecting the Purex, Redox, and UO{sub 3} Plants must be integrated with the Continuity of Operations Program. Since the primary separations plants feed the 234-5 Facility, t… more
Date: December 7, 1959
Item Type: Refine your search to only Report
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CONTROL OF OXYGEN CONCENTRATION IN A LARGE SODIUM SYSTEM

Description: Data on the performances of two types of cold traps in the 50,000-lb radioactive sodium system at the SRE are tabulated. The rates were determined when trap inlet oxygen concentrations were at 8 to 10 parts per million. Oxygen concentration was readily controlled to 8 ppm using a cold trap. Extraction of oxygen from sodium by zirconium at 1200 deg F (hot trapping) reduces the concentration below the limit of detection, i.e., oxide solubility saturation temperature below 225 deg F. The theoretic… more
Date: December 1, 1959
Creator: Hinze, R B
Item Type: Refine your search to only Report
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Control Rod Positions for Criticality. Section I. 5032-EFPN. Eigth Performance. Core I, Seed 1. Test Results DL-S-149, T-550130

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at ambient temperatures. The critical rod bank position and bank worths for four different control rod bank rod configuration were determined after 5032 EFPH's of operation. The value were corrected to a reactor coolant temperature of 145 F and a pressure of 400 psig. The bank worths were corrected to 145 F so that the results of the performance could be compared with the results of pre… more
Date: December 9, 1959
Creator: McTish, James M.
Item Type: Refine your search to only Report
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Corrosion of INOR-8 and Inconel Dissolver Components of the Fluoride-Volatility Process

Description: The corrosion of INOR-8 and Inconel dissolver components used in the fluoride volatility process for the dissolution of zirconium with anhydrous HF in molten salts was investigated. Ten dissolution runs were made using simulated subassemblies formed from Zircoloy-2. The dissolver and components were made from INOR-8. Both the dissolver vessel and draft tube were examined several times during the series of runs. The solids which formed at different areas in the system were also analyzed. The res… more
Date: December 30, 1959
Creator: Fink, Frederick W.
Item Type: Refine your search to only Report
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Corrosion of Stainless Steel in Thorex Process Solutions

Description: The corrosion of 304L and 309SCb stainless steel was studied in HF--HNO/ sub 3/ solutions proposed for the Thorex process. Except for the dissolving and waste evaporation steps in the Thorex process, corrosion of 304L and 309SCb is not expected to exceed that experienced in the Purex process. To minimize the high initial corrosion rate of 309SCb in the boiling HF-- HNO/sub 3/ dissolving solution, a heel of thorium should be maintained in the dissolver. The corrosion rate of 304L in the low acti… more
Date: December 1, 1959
Creator: Kranzlein, P. M.
Item Type: Refine your search to only Report
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