UNT Libraries Government Documents Department - 18 Matching Results
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- Fabrication and Properties of Extruded Silver-Cadmium Control Rods
- The production of cross-type control rods having a span of 4-7/8 in., and an arm thickness of 1/8 in., was studied. Extrusion techniques were developed for producing cross-type control rods from each of two alloys; one containing 75% silver-25% cadmium, and the other containing 67% silver-30% cadmium-3% copper. Fabrication of the extruded crosses into clad control rods for the Mark I naval reactor was attempted. A set of unclad control rods for the Zero Power Reactor was produced. The effect of copper, nickel, aluminum, palladium, and indium, singly and in various combinations, on the physical and mechanical properties of silver cadmium was studied. Data are given on the work hardening and annealing of binary silver-cadmium alloys, and on the precipitation hardening of certain complex silver cadmium alloys. A materials specification and suggested fabrication procedure were established for nickel-clad extruded silver-cadmium control rods.
- Zrclad Zirconium-Uranium Alloy Rod for Heat Thru-Put Test
- The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.
- The Manufacture of Aluminum Clad Aluminum-Plutonium Alloy Irradiation Specimens
- This report describes the manufacture of 25 Aluminum clad, 10 w/o plutonium-aluminum alloy and 5 w/o plutonium-aluminum alloy cored specimens for Argonne National Laboratory-University of California irradiation tests in the Materials Testing Reactor. The manufacturing method: preparation of cores and cladding material, assembly and welding of compacts, outgassing, roll bonding, shearing, identification marking and final fabrication into napkin "rings" is described in detail. Of ninety-six specimens fabricated, ninety-one were completed as finished specimens. Forty-four of these contained 5 w/o plutonium alloy cores and forty-seven contained 10 w/o plutonium alloy cores. Five specimens ere rejected for bond blistering.
- Physical and Mechanical Properties of Some Aluminum-Lithium Alloys
- The results of this study are tabulated in Summary Tables A and B below. For the most part, these values were read from smoothed curves drawn thru the plotted experimental data. The values for aluminum (i.e., 0 w/o Li) were taken from the 1948 Edition of the ASM Metals Handbook. The room temperature properties are reported for lithium contents of 0, 3.5, 7 and 10 weight per cent. In the case of the high temperature properties, there were insufficient data to allow extrapolation and interpolation to pre-chosen compositions: these properties are therefore reported only for the compositions of the actual samples.
- Metallurgy Division Quarterly Report [for] October, November, and December, 1952
- This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses (1) water-cooled reactors, (2) liquid metal-cooled reactors, (3) reactor development - fuel metallurgy, (4) reactor development - component metallurgy, (5) basic metallurgy, (6) basic ceramics, (7) aqueous corrosion, and (8) applied metallurgy.
- Helium Leak Detector Test for Hanford And Savannah River Fuel Slugs
- The Helium Leak Detector Test provides a method for detecting the presence of minute holes, cracks, fissures, etc. in the aluminum jackets of Hanford and Savannah River reactor fuel slugs which would allow moisture to penetrate to the uranium during reactor operation.
- Reactor Engineering Division Quarterly Report September 1, 1952 through November 30, 1952
- Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
- Chemistry Division, Section C-1, Quarterly Report July, August, and September 1952
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- Chemistry Division, Section C-1, Summary Report for April, May, And June 1952
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- The Decomposition of Light and Heavy Water Boric Acid Solutions by CP-3' File Radiations
- The behavior of light and heavy water solutions of boric acid toward pile radiations has been investigated as a function of boric acid concertation. A study has also been made of the effect of hydrogen, hydrogen peroxide, and potassium iodide on the radiation stability of boric acid solutions.
- A Capsule Design for Experimental High-Flux Irradiations Of Fuel Materials
- New reactors presently in design or construction stages, as well as revised operating procedures for existing reactors, have shown an increasing emphasis on extending the exposure time of the reactor fuel elements. However, operating experience at Hanford, as at other installations, has demonstrated that as the amount of burn-up in uranium metal is increased an increase is also noted in operational difficulties resulting from the dimensional behavior of the fuel. During reactor irradiation uranium slugs or rods have been observed to change in length and diameter, to warp, and to develop surface roughening.
- The Thermal Neutron Cross Section Of 9.2h Xe135 : Supplement to Report CP-2782
- In this report it reviews a possible declassification of the content of report CP-2782 (February 15, 1945) that presents the data of the most careful measurements of the thermal neutron cross section of 9.2h Xe135 and re-evaluation of the particular methods of measuring neutron flux employed in this experiment had been made for other purposes.
- Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature
- This report describes corrosion rate of uranium in hydrogen-saturated water appears to be constant with respect to time after a brief induction period and to involve only one type of over-all reaction, in which pitting effects are slight or nonexistent.
- Chemistry Division, Section C-1, Summary Report For October, November and December 1951
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- Reactor Engineering Division Semiannual Report December 1, 1951 through May 31, 1952
- This report describes the construction of a reactor and the research conducted in the reactor such as solid fuel and liquid fuel research, boiling reactor experiments, CP-6 bond testing program, and water quality control experiments for CP-6 program.
- Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952
- Report issued by the Argonne National Laboratory discussing the Conference on the Toxicity of Carbon 14. At the outset of the meeting it was emphasized that the group was brought together to discuss work which had a bearing on the toxicity of C14 compounds used either clinically or industrially, and the hope was expressed that the group might be able to reach some conclusions on these matters. This report includes tables.
- Heat Generation in Irradiated Uranium
- Report issued by the Argonne National Laboratory discussing the heat generation of irradiated uranium. Methods of heat production in uranium are presented. This report includes tables, and illustrations.
- Calculations on U235 Fission Product Decay Chains
- Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).