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Testing of Fuel Element Parts and Assemblies by the Radiographic Method

Description: Concurrently with the production of canned uranium slugs for pile operation there arises the problem of nondestructive testing so that no slug which may fail structurally during operation be placed in the pile. The ultimate goal of any such testing program is to devise nondestructive testing methods which will eliminate defective slugs. A secondary goal of the testing program is to learn as much as possible about the construction of the canned slug so that the mechanisms of failure can be under… more
Date: July 1, 1954
Creator: VanderLaan, Robert H.
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report January, February, and March, 1954

Description: Progress is reported on (1) direct cycle boiling reactor studies, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) fluidization studies, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: May 1, 1954
Creator: Lawroski, Stephen; Rodger, W. A. & Vogel, R. C., 1928-
Partner: UNT Libraries Government Documents Department
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Differential Thermal Analysis of Irradiated Diamond and Silicon Carbide

Description: It was demonstrated by differential thermal analysis (DTA) that: 1. Catastrophic amounts of energy can be stored in diamond. 2. Even at low irradiations, the release takes place over serval hundred degrees, indicating a spectrum of activation energies. 3. At higher irradiations, the stored energy release is considerably less than the increased energy contents and seems not to have been completely released even at the highest temperatures reached. 4. There is some indication of an increased heat… more
Date: December 1, 1954
Creator: Primak, William, 1917-
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report October, November, and December, 1953

Description: Progress is reported on (1) experimental breeder reactor program, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) denitration of uranyl nitrate in a fluidized bed, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: January 1, 1954
Creator: Lawroski, Stephen & Stevenson, C. E.
Partner: UNT Libraries Government Documents Department
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Corrosion and Stability Tests on Chemical Poisons in Higher-Temperature Water

Description: Corrosion-stability tests have been made in static autoclaves at 500 and 600F on solutions of compounds having high neutron cross sections to evaluate their usefulness for shutdown purposes. The only compound tested which appeared to be completely stable in 600F water was boric acid. Limited corrosion data did not show it to cause excessive corrosion of zirconium or stainless steel.
Date: September 1, 1953
Creator: Breden, Calvin Rudolph, 1901- & Abers, Alma
Partner: UNT Libraries Government Documents Department
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Development of a Process to Produce Zirconium Hanford Type Process Tubing by Roll Forming And Inert Arc Welding

Description: The development of methods which were successful in producing zirconium Hanford type process tubing by roll forming and inert are welding (He) flat strip to which appropriate rails had ben previously attached by resistance welding is described in this report. Grade 2 drip arc melted crystal bar material was used.
Date: May 1, 1953
Creator: Noland, R. A. & O'Keefe, G. B.
Partner: UNT Libraries Government Documents Department
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Chemistry Division, Section C-1, Summary Report for April, May, And June 1952

Description: 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.
Date: August 1, 1952
Creator: Osborne, D. W.
Partner: UNT Libraries Government Documents Department
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Intergranular Crack Propagation Rates in Sensitized Type 304 Stainless Steel in an Oxygenated Water Environment

Description: Intergranular stress-corrosion crack (IGSCC) propagation rates were measured in three heats of sensitized Type 304 stainless steel (SS) as a function of sensitization in an environment of high-purity water with 8 ppm oxygen, using a fracture mechanics approach. Specimens were sensitized using controlled furnace heat treatments and the degree of sensitization was measured by the electrochemical potentiokinetic reactivation (EPR) method. Active loading tests were performed on standard specimens … more
Date: December 1, 1983
Creator: Park, J. Y. & Shack, W. J.
Partner: UNT Libraries Government Documents Department
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