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Calculation of Temperatures in a Two Pass Cylindrical Core Using an IBM-704 Computer

Description: Attached to this report is a letter from Raymond R. Schiff, containing pertinent information, dated Jan. 28, 1957. 2p. (WAPD-S5W-NA-1451. The input for the program includes radial and axiai power distributions and rules for combining them into three-dimensional power distributions, radially and axially variable local peaking factors, engineering hot channel factors, and geometrical data. The output consists of the average inlet and outlet temperatures for each pass, the maximum relative heat fl… more
Date: November 1, 1956
Partner: UNT Libraries Government Documents Department
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Contribution to the Study of Electrolytic Polishing of Uranium Alloys; CONTRIBUTION A L'ETUDE DU POLISSAGE ELECTROLYTIQUE D'ALLIAGES D'URANIUM

Description: The electrolytic polishing of uranium-rich U-Nb and U-Zr alloys was investigated. The Disa-Electropol'' electrolytic polisher was used in the tests with the electrolyte being a mixture based on perchloric acid and alcohol. The effects of the polishing time and the potential used and the relationships between voltage and time and between current and voltnge were determined for U-Zr alloys. The results showed that the electrolyte used gave relatively goed results for U-Zr alloys. The same techniq… more
Date: November 1, 1956
Creator: Van Asbroeck, P.
Partner: UNT Libraries Government Documents Department
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Dingot Program

Description: This report discusses production testing of dingot material. Advantages and disadvantages of uranium produced by the dingot process are noted.
Date: November 1, 1956
Creator: Reinker, P. H.
Partner: UNT Libraries Government Documents Department
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Enrico Fermi Fast Breeder Reactor Plant

Description: This report contains a description of the reactor plant portion of the Enrico Fermi Atomic Power Plant, with emphasis on the reactor system. Since this plant contains a developmental reactor, emphasis has been placed on reactor safety and on achieving reliable operation. The design is conservative and is flexible enough to permit incorporation of the results of developmental programs, which include nonnuclear, full-scale component test facility operations, and nuclear experiments, such as criti… more
Date: November 1, 1956
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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HIGH-ENERGY PARTICLE DATA. VOLUME I

Description: No Description Available.
Date: November 1, 1956
Creator: Willis, B H & Stableford, C V
Partner: UNT Libraries Government Documents Department
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Internal Bremsstrahlung and Decay Scheme of Sb¹¹⁹

Description: The spectrum and yield of internal bremsstrahlung accompanying electron capture form S- and P-states in sb119 were measured and compared with the theory of Glauber and Martin. sb119 was obtained as the daughter from el l9 produced by the ~b(dx,n )~ell9 and Sn(a, xn)~ell9 reactions. The decay is by orbital electron capture to the 23.83-key state in Sb¹¹⁹. The following results were obtained: Sb¹¹⁹ half life, 38.0 hr ; Sb¹¹⁹ -Snl l9 decay energy. 579 f 20 kev; half life of the 23 83-kev state and… more
Date: November 1, 1956
Creator: Olsen, James L. & Mann, Lloyd G.
Partner: UNT Libraries Government Documents Department
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Investigation of the Effect of Fuel Filler Surface Conditioning Upon Fuel Element Properties

Description: The results of two test runs conducted with surfaceconditioned fuel fillers are reported to evaluate the effect upon diffusion zone thickness, bond strength, and corrosion properties of Zircaloy-2 clad U--1O wt.% Nb. Results indicate that there is no significant effect of fuel surface condition upon diffusion zone thickness. The bonding interface of the rolled fuel element has greater strength than either the clad or the rod. The corrosion data were inconclusive because of the small number of t… more
Date: November 1, 1956
Creator: Weiss, S.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Semiannual Progress Report for Period Ending April 10, 1956

Description: Tests of materials for use in liquid-metal and fused-salt systems were continued. Corrosion tests, penetrability tests, thermal tests, and solubility tests were conducted on structural alloys, brazing alloys, special alloys, cermets, carbides, nitrides, and rare-earth oxides. Progress in loop design and testing is reported. Hastelloy W creep and stress testing and general welding and brazing tests and investigations are reported. Development work is reported in nickel-molybdenum base alloys and… more
Date: November 1, 1956
Partner: UNT Libraries Government Documents Department
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The Movement of Radiostrontium Through Natural Porous Media. Progress Report No. 2 Covering Period July 1, 1955 to June 30, 1956

Description: The feasibility of discharging radioactive wastes into underground formations is dependent on the predictability of the movement of certain hazardous radioisotopic components. This progress report examines several theories concerned with the equilibria and kinetics of ion-exchange as they apply to estimating the rate of underground movement of radiostrontium. Laboratory studies were conducted with the objective of testing the applicability of these theories to estimating the displacement and di… more
Date: November 1, 1956
Creator: Orcutt, R.G.; Kaufman, W.J. & Klein, G.
Partner: UNT Libraries Government Documents Department
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MTR Technical Branch Quarterly Report, Third Quarter

Description: Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
Date: November 1, 1956
Creator: Conner, W. P.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During October, 1956

Description: A report about the use of clad specimens to successfully measure the thermal conductivity of irradiated uranium.
Date: November 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During October 1956

Description: Research is reported in the development of materials for Hanford reactors, development, of Al-clad fuel elements. plant assistance to MCW, reactions between HiO and Zr alloys, general fuel element development, Zr --U alloy studies, corrosion of Zr, reactor materials development, physical metallurgy, development of PWR, and Na-- Ta compatibility at high temperatures. (T.R.H.)
Date: November 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Shearing Irradiated Uranium Plates

Description: Natural U plates that were irradiated to 600 and 1500 Mwd/t were cut under water by a guillotine-iype shear. Irradiation reduced the force required for shearing to 50% of that required for unirradiated U. Measurements were made of radioactivity released to treated and untreated water in which the cut sections were stored. (auth)
Date: November 1, 1956
Creator: Delicate, W. S.; Osterman, E. J. & Zeh, C. W.
Partner: UNT Libraries Government Documents Department
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