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Producibility of an Alloy of Columbium with One Percent Zirconium

Description: Abstract. Proven mineral resources show that niobium is the most abundant of the refractory metals and extraction capacity is adequate to meet foreseeable requirements. Approximately four tons of Nb-1% Zr alloy were melted, forged, drawn, and rolled to produce various mill forms and relatively large die impression forgings. It was demonstrated that the Nb-1% Zr alloy is readily amenable to melting, primary working, and secondary working using standard equipment available in the specialty steel … more
Date: December 9, 1959
Creator: Raring, L M
Partner: UNT Libraries Government Documents Department
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A PROPOSAL FOR THE CONTROLLED RELEASE OF STORED ENERGY IN THE MTR REFLECTOR GRAPHITE

Description: A study of the stored energy buildup in the MTR reflector graphite and a program of controlled energy release is presented. Calculations, based on measurements of samples from the pebble zone show that an inadvertent spontaneous stored energy release would cause a temperature rise of 90 deg F in the pebble zone. The maximum transient structure temperatures resulting from a worst credible accidental release of energy would be less than allowable at present (except for possible damage to neutron … more
Date: December 9, 1959
Creator: Fast, E.; Smith, E.O. & Ford, J.D.
Partner: UNT Libraries Government Documents Department
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Temperature Measurement in Operating Reactors: In-Reactor Temperature Measurement Associated With Fuel Element Testing

Description: The Fuel Development operation at Hanford uses a variety of in-reactor facilities to test experimental and prototypical fuel elements. High pressure-high temperature water loops in constant use are the 6 in. {times} 9 in. ETR core facility, the 3 in. {times} 3 in. ETR reflector facility and four front-to-rear loops in the 100-K East reactor at Hanford. Low pressure water cooled test facilities in use are located in the MTR the various Hanford reactors. Stainless steel sheathed the thermocouples… more
Date: December 9, 1959
Creator: Wheeler, R. G.
Partner: UNT Libraries Government Documents Department
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Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements

Description: The current interest in a tube-in-tube type Zircaloy-2 clad UO2 fuel element for use in the power reactors provided the incentive for a study of the dissolution of cladding from an annular space. The objectives of the study were to compare the estimated rate of dissolution in the annuli with rates on fully exposed metal. Because of an interest from the design standpoint, heat balance data from the study are reported.
Date: December 9, 1959
Creator: Smith, P. W.
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Nuclear Instrumentation Operation During Plant Operation. Section I. First Performance. Core I, Seed 1. Test Results DL-S-309, RNI-41

Description: The purpose of the test was to evaluate the operation of the Nuclear Instrumentation Power Range Amplifier during start up. While the station was operating at a gross load of 16.5 megawatts, a variation of 0, 8.5, 2.7 and 4.4 existed between the compensated ion chamber currents (CIC) and the test currents for channels A, B, C and D respectively. The off site modifications to channel C power range amplifier did not cause the ion chamber current and test current to be the same at 16.5 megawatts g… more
Date: December 8, 1959
Partner: UNT Libraries Government Documents Department
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Study of Factors Influencing Ductility of Iron-Aluminum Alloys. Monthly Letter Report No. 8, 15 March 1959 to 15 March 1960

Description: Studies are being made on the effects of variation of aluminum content, heat treatment, surface preparation, and other metallurgical factors on the room temperature ductility of Al-- Fe alloys. It is estimated that approximately 65 percent of the proposed research has been completed over the first eight and one-half months of the contract period.
Date: December 8, 1959
Creator: Perkins, Frank C. & Nachman, J. F. (Joseph F.)
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Examination of a severely pitted X-8001 alloy clad fuel element (RM-303)

Description: An X-8001 clad, I & E natural uranium fuel element irradiated in tube 2762D to 886 MWD/T was discharged in February 1959 and sent to Radiometallurgy Laboratory for examination at the request of Irradiation Processing Department. After discharging tube 2762D which was loaded with X-8001 clad fuel elements, a fuel element (KL018D) was observed to be very badly pitted. Visual and photographic inspection revealed the pits had penetrated into the AlSi layer. The pitting appeared as the result of ero… more
Date: December 7, 1959
Creator: McMahan, M. E.
Partner: UNT Libraries Government Documents Department
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Examination of Components for Crud and Corrosion. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-155, T-612080

Description: The purpose of the test was to observe the extent and location of corrosion, crud deposits and defects in components of the primary fluid system and its auxiliaries. This observation will allow an estimate to be made of the future behavior of the affected parts. The test also provides for obtaining corrosion products and crud samples for analysis as necessary for planning remedial actions. This test was limited to the 1D Main Coolant Pump which failed November 3, 1958. The pump failed after 223… more
Date: December 7, 1959
Creator: Muldoon, James B.
Partner: UNT Libraries Government Documents Department
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The Fast Effect in a Beryllium Moderated Reactor

Description: The effect of the (n, 2n) and (n, o<) reactions on the neutron economy of a beryllium moderated reactor is investigated.
Date: December 7, 1959
Creator: Novak, P. E.
Partner: UNT Libraries Government Documents Department
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Main Coolant Pump Performance Test. Section I. First Performance. Core I, Seed 1. Test Results DL-S-290, T-641326

Description: The purpose of the test was to obtain performance data for the main coolant pumps on fast and slow speed at various coolant temperatures. The 1A, 1B and 1C pump performances on both fast and slow speed were approximately as shown in the manufacture's predicted performance curve. The 1D pump performance was below the manufacturer's predicted flow efficiency, line current and hydraulic horsepower on both fast and slow speeds.
Date: December 7, 1959
Creator: Edwards, Gerald E.
Partner: UNT Libraries Government Documents Department
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Equilibrium Extraction Characteristics of Alkyl Amines and Nuclear Fuels Metals in Nitrate Systems. Progress Report No. V for the Period July 1 - September 30, 1959

Description: Extraction of HNO3 by triaryl amine was studied by equilibrating equal volumes of aqueous and organic phases at 25C. At HNO3 concentrations of 2 to 10 N the acid in the organic phase in excess of that equivalent in the amine concentration was proportional to the concentration of HNO3 in the equilibrated aqueous phase. other workers report similar results with nitric acid and tri-n-octyl amine in benzene. Zirconium extractions carried out at 10g Zr/1 with 0.35 M TLA nitrate in toluene showed a f… more
Date: December 4, 1959
Creator: Mason, Edward A. (Edward Allen), 1926-1994. & Vaughen, Victor C.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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The Determination of Decontamination Factors for Radioisotopes Through Lithium Hydroxide Resin. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-277-S, RNI-22

Description: The purpose of the test was to obtain data on the decontamination factors for Cesium-136, Cesium-137, Strontium-92, one hour gross iodine and Iodine-131. This data will be used to determinate efficiency of lithium hydroxide resin for removing radioactive cations and anions. The denomination factors for a particular demineralizer using lithium hydroxide resign were found to vary for different radioisotopes. This variation was from 2.3 for Cesium136 to 77,000 for gross iodine.
Date: December 3, 1959
Creator: Strauos, Roger O.
Partner: UNT Libraries Government Documents Department
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Neutron-Flux Measurements in a Flat Plate Fuel Element

Description: The equipment and experiments performed to measure the thermal-neutron- flux distribution in a fuel assembly of an experimental loop mock-up of a gas:cooled reactor at the Battelle Research Reactor (BRR) are described. The loop was located adjacent to the core of the BRR and contained one fuel assermbly composed of seven flat fuel plates each containing approximately 29.5 g of U/sup 235/. The plates consisted of a core 0.050 in. thick of UO/sub 2/ dispersed in Type 347 stainless steel and clad … more
Date: December 3, 1959
Creator: Morgan, W.R.; Anno, J.N. Jr. & Chastain, J.W. Jr.
Partner: UNT Libraries Government Documents Department
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Effects of 100-K water plant expansion on Panellits and orifices

Description: The information reported here was requested by M.H. Schack, Facilities Engineering Operation. It pertains to the 100-K water plant expansion Project CG-775. In this project, cooling water pumping capacity will be increased from 178,000 GPM existing to 188,000 GPM and 200,000 GPM for five and six modified pumps respectively. Effects of increased through-put on process tube flow metering elements and on the reactor Panellit gauges have been examined. This information was required to determine cos… more
Date: December 2, 1959
Creator: Stepnewski, D. D.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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