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Waste Treatment and Disposal Progress Report for June and July 1961

Description: 7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scaven… more
Date: October 24, 1961
Creator: Blanco, R. E. & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid

Description: The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several type… more
Date: October 1, 1961
Creator: Clark, A. T., Jr.; Meyer, L. H.; Owen, J. H. & Rust, F. G.
Partner: UNT Libraries Government Documents Department
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METALLURGY DIVISION ANNUAL REPORT FOR 1961

Description: 8 < 8 7 8 7 < 5 8 6 ; : 9: 2 8 9 9 ; ; < 9 : 9 : 8 8 I of transformation and fusion, of U and U- fissium alloys were completed during the year. Data are also included on cladding penetration by molten U-fissium alloys and molten Pu fuel. Irradiation studies of U-fissium and Ufissium-Zr alloys were conducted. Progress is reported on the development of methods and equipment for remote refabrication of EBR-II fuel. Development and Fabrication of EBR-I Core IV Fuel Elements. A program to investigat… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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SNAP Programs. Quarterly Progress Report No. 6, January 1 through March 31, 1961. Task 6. Fuel Technology Development Program

Description: Isotope power sources are being developed for use in thermionic and thermoelectric power generators for space applications. Suitable radioisotope fuels and heat source containment capsules are being designed for SNAP-type generators with land, sea and space applications. Curium242 and Plutonium-238 are currently being investigated, and methods for purification, compound conversion and fuel form are being established. A Heavy Elements Processing Facility capable of handling and preparing gram qu… more
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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Final Report: Radiation-magnetohydrodynamic evolution and instability of conductors driven by megagauss magnetic fields

Description: We are pleased to report important progress in experimentally characterizing and numerically modeling the transformation into plasma of walls subjected to pulsed megagauss magnetic fields. Understanding this is important to Magnetized Target Fusion (MTF) because an important limitation to the metal liner approach to MTF comes from the strong eddy current heating on the surface of the metal liner. This has intriguing non-linear aspects when the magnetic field is in the megagauss regime as needed… more
Date: October 22, 2008
Creator: Bauer, Bruno, S. & Siemon, Richard, E.
Partner: UNT Libraries Government Documents Department
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High Burn-Up Tests of U-Al Fuel Elements

Description: A series of irradiation tests were performed on the High Flux Beam Reactor fuel elements. The U--Al fuel elements contained 30 to 40 wt% U and 3% Si. Burnup ranged from 20 to 50%. A summary of the results is given. (C.E.S.)
Date: October 31, 1964
Creator: Weeks, J. R.; McRickard, S. B. & Gurinsky, D. H.
Partner: UNT Libraries Government Documents Department
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FURTHER RESULTS ON THE PRODUCTION OF NEUTRAL MESONS BY PHOTONS

Description: Further measurements have been made on the photoproduction of neutral mesons using the gamma-gamma coincidence technique. New data have been obtained on the gamma-gamma correlation curves in beryllium. The angular distribution of the photo mesons in Be has been determined and found to be strongly peaked forward. The dependence on the atomic number A of production has been found to obey an A{sup2/3} law. Some data obtained for production in hydrogen show that the pi-zero and pi-plus production c… more
Date: October 1, 1951
Creator: Panofsky, W.K.H.; Steinberger, J. & Steller, J.
Partner: UNT Libraries Government Documents Department
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Reactor Development Quarterly Progress Report. 4000 Program

Description: The status of Experimenial Boiling Water Reactor development is reviewed. Shell testing, control mechanism development, fuel corrosion, and dimensional stability studies, and design consideration to facilitate D/sub 2/O operation are discussed. Fuel plate and subassembly fabrication, corrosion, and radiation damage studies were continued. Reactor water filtration, purification, and induced activity are considered. High-temperaiure operational tests were run on Experimental Breeder Reactor mecha… more
Date: October 31, 1955
Creator: McLain, S. comp.
Partner: UNT Libraries Government Documents Department
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REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR PERIOD JULY 1, 1954 THROUGH SEPTEMBER 30, 1954

Description: Reactor Programs. The design of the Boiling Experimental Reactor is described. The Borax-1 reactor was intentionally destroyed by suddenly adding 4% excess reactivity. Design of the Borax-II reactor is described. It will be used for studies of transient behavior and steadystate operation as a steam producer. A preliminary design configuration has been established in EBR-II employing central, inner, and outer blankets. Fuel geometries including a smaller pin-type element are being investigated. … more
Date: October 15, 1954
Partner: UNT Libraries Government Documents Department
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The Tensile Strength of Solid-State Bonded Aluminum and Nickel-Plated Uranium

Description: To aid in the evaluation of solid-state bending techniques for cladding natural-uranium fuel-element cores with aluminum, tensile specimens, 1/4 in. in diameter and 3 in. long were made and tested. Results show that these techniques are capable of producing satisfactory bonds between aluminum and nickel-plated uranium. Pressing conditions of 1 min at 950F and 6000 psi produced consintent bond strengths equal to the yield strength of 25 aluminum. When optimum bonding conditions are used, anodic … more
Date: October 21, 1954
Creator: Saller, H. A.; Dickerson, R. F. & Carlson, R. J.
Partner: UNT Libraries Government Documents Department
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Characterization of Surfactants in Aluminum-Uranium Fuel Reprocessing Solutions

Description: Surface active materials in aluminum nitrate-nitric acid fuel reprocessing solutions were characterized. Polymerized silica, zirconium- modified silica and soluble dibutyl phosphate species were found to contribute to stable emulsion formation. These surfactants were reduced in effectiveness by added acid. (auth)
Date: October 20, 1959
Creator: Cannon, R. D.
Partner: UNT Libraries Government Documents Department
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The Effect of Electronic Paramagnetism on Nuclear Magnetic Resonance Frequencies in Metals

Description: Observations on the shifts of nuclear resonances in metals (Id {sup 7}, Na {sup 23}, Ou {sup 63}, Be {sup 9}, Fe {sup 207}, A1 {sup 27} and Oa {sup 69}) due to free electron paramagnetism; comparison with theoretical values.
Date: October 31, 1950
Creator: Townes, C. H.; Herring, C. & Knight, W. D.
Partner: UNT Libraries Government Documents Department
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A SHIELDED METALLOGRAPH FOR REMOTE METALLOGRAPHY. Topical Report- Metallurgy Program 6.10.6

Description: A unique concept is featured in the adaptation of a Bausch and Lomb Research Metallograph for remote metallography at Argonne National Laboratory. The metallograph is placed outside and adjacent to the metallographic preparation hot cell, and only the microscope section is shielded. This arrangement results in the decisive advantages of simplified adaptation for remote operation, and unaltered optical system, and greatly reduced shielding bulk. A mechanical transfer system shuttles the irradiat… more
Date: October 1, 1957
Creator: Brown, F. L.; Haaker, L. W.; Paine, S. H. & Blomgren, R. A.
Partner: UNT Libraries Government Documents Department
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Underground Corrosion of Activated Metals in an Arid Vadose Zone Environment

Description: The subsurface radioactive disposal site located at the Idaho National Engineering and Environmental Laboratory contains neutron-activated metals from nonfuel nuclear-reactor- core components. A long-term corrosion test is being conducted to obtain site-specific corrosion rates to support efforts to more accurately estimate the transfer of activated elements in an arid vadose zone environment. The tests use nonradioactive metal coupons representing the prominent neutron-activated material burie… more
Date: October 24, 2001
Creator: Adler Flitton, M. K.; Mizia, R. E. & Bishop, C. W.
Partner: UNT Libraries Government Documents Department
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An Assessment of Recycled Refractory Material Performance After Two Years of Service in a Carbon Bake Furnace

Description: Material removed from carbon bake furnaces used to manufacture anodes for the production of aluminum metal has historically been disposed by landfill. This material is composed primarily of 50% alumina refractory. in 1997, Alcoa completed a highly successful program to reuse the spent refractories in castables for carbon bake furnace headwalls and flooring, as roadbed aggregate, and in other internal applications. This program recycled/reused 11,000 metric tons of used refractory material (99% … more
Date: October 27, 1999
Creator: Schubert, N.; Bennett, J.P. & Kwong, K.S.
Partner: UNT Libraries Government Documents Department
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Ceramics Research and Development Operation Quarterly Report, October- December 1962

Description: CERAMICS RESEARCH AND DEVELOPMENT OPERATION QUARTERLY REPORT, OCTOBERDECEMBER 1962. Pu/sub 2/S/sub 3/ melted congruently at 1725 450 deg C in a 10 un. Concent 85% C under vacuum or argon and was stable to 2300 un. Concent 85% C in argon. Pu/sub 2/S/sub 3/ was not attacked by boiling, demineralized water. PuN melted congruently at 2750 450 deg C in a 75 un. Concent 85% C under nitrogen (1 atm), but dissociated at 2600 un. Concent 85% under argon or helium. Plutonium carbides and oxides of variou… more
Date: October 31, 1963
Partner: UNT Libraries Government Documents Department
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Specifications and Procedures Used in Manufacturing U$sub 3$O$sub 8$- Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Description: A thin plate-type element containing a dispersion of 20% enriched U/sub 3/O/sub 8/ was developed and successfully used in the 5-Mw pool-type research reactor at the Puerto Rico Nuclear Center. The underlying criteria that guided the design are presented. The technological factors, such as compatibility, corrosion resistance, and irradiation behavior, which led to the selection of U/ sub 3/O/sub 8/ as the fissile compound and aluminum as the cladding and matrix material, are reviewed. The fabric… more
Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F. Jr. & Beaver, R. J.
Partner: UNT Libraries Government Documents Department
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