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0-2 kv Flash Tube Supplies

Description: The power supplies designed and constructed to power high-intensity flash tubes are described. Three supplies, capable of charging 100 mfd to 2 kv with a repetltion rate of not less than 0.8 sec, are operated remotely from a control panel containing 3 powerstats. The power supplies are full wave center trapped rectifiers employing silicon rectifiers. (M.C.G.)
Date: March 15, 1962
Creator: Miller, D. M.
Partner: UNT Libraries Government Documents Department
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0-2 kv Flash Tube Supplies

Description: In order to perform the various experiments with a bubble chamber, a high intensity flash tube is used. This report briefly describes the power supplies designed and constructed to power these lamps.
Date: March 15, 1962
Creator: Miller, D. M.
Partner: UNT Libraries Government Documents Department
open access

6 kv Capacitor Charging Supply

Description: The power supplies designed and constructed to power high intensity flash tubes used in bubble chamber experiments are briefly described and are accompanied by a schematic diagram of the layout. (D.C.W.)
Date: March 15, 1962
Creator: Miller, D. M.
Partner: UNT Libraries Government Documents Department
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6 kv Capacitor Charging Supply

Description: The power supplies designed and constructed to power high intensity flash tubes used in bubble chamber experiments are briefly described and are accompanied by a schematic diagram of the layout. (D.C.W.)
Date: March 15, 1962
Creator: Miller, D. M.
Partner: UNT Libraries Government Documents Department
open access

Alkali Metal Physical Properties Program at Pratt & Whitney Aircraft-CANEL

Description: The favorable combination of physical properties such as heat capacity, viscosity, electrical resistivity, thermal conductivity and high temperature liquid range make alkali metals, in principle, among the best heat transfer fluids available for use in nuclear reactor and other esoteric powerplant systems. Unfortunately, many of these properties are not known with sufficient certainty in the high temperature region to permit optimization of design criteria for developing maximum efficiency coo… more
Date: June 15, 1962
Creator: Kapelner, S. M. & Cleary, Robert E., 1920-
Partner: UNT Libraries Government Documents Department
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Annual Progress Report on Fuel Element Development for FY 1962

Description: Activities in a project aimed at the improvement of fuel elements for high flux test reactors are reported. The investigation of new fuel compositions, distributions, and geometries is being undertaken to increase fuel life, to improve the flux distribution, and to provide a means of safely reaching higher reactor operating power and power density in these reactors. The effects of nuclear irradiation on the fuel and structural materials is being studied to predict the performance of these mater… more
Date: August 15, 1962
Creator: Gibson, G. W. & Francis, W. C.
Partner: UNT Libraries Government Documents Department
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Artificial cooling of the Columbia River by dam regulation, 1961

Description: This report details benefits of an increase in the flow of water from the lower depths of Grand Coulee Reservoir which used to lower river temperatures at HAPO. A net average daily reduction of over 1.7{degree}C resulted at HAPO. The peak reduction was over 4.0{degree}C. The net production gain from temperature change was 13,350 MWD. The cost of control was: Grand Coulee Charges (Estimated) $37,000, and other 3,500, for a total of $40,500.
Date: June 15, 1962
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Calculation of the Vibrational Frequencies of Ethylene

Description: In this report, approximations which have been shown to simplify the calculation of the normal modes of paraffin hydrocarbons are tested for olefinic hydrocarbons by application to C2H4, CH2CD, C2D4. The results indicate that the method should suffice for the low-frequency models below about 0.1 ev energy, and may be adequate for all vibrations as far as he needs of neutron scattering are concerned,
Date: May 15, 1962
Creator: Goin, R W
Partner: UNT Libraries Government Documents Department
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Capsule Irradiation of Unalloyed Uranium at High Temperatures

Description: Abstract: Cast and Wrought specimens and restrained wrought specimens of unalloyed uranium were irradiated in the Materials Testing Reactor, as the first in a series of experiments to develop fuel materials for sodium cooled reactors.
Date: August 15, 1962
Creator: Harrington, D. G. & Newton, J. B.
Partner: UNT Libraries Government Documents Department
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Comparative Study of PuC-UC and PuOâ‚‚-UOâ‚‚ as Fast Reactor Fuel

Description: From abstract: "This section, Part II, extends the comparison of two ceramic fuel systems to include the fuel cycle cost comparison in greater detail particularly with respect to fabrication and reprocessing unit costs."
Date: November 15, 1962
Creator: Collins, G. D.
Partner: UNT Libraries Government Documents Department
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Control rod studies (Tory II-C)

Description: This memorandum outlines the area of interest in connection with the SSBN launch application, on modification of the Tory II-C control rod system; and suggest a plan of development of information. Because of the very limited space for overall missile length, little room is available for control rod motion upstream from the core. Shortening the rod stroke, and the total length occupied by control rod mechanism., becomes very desirable. Changes in the actuator and linkage mechanism will clearly h… more
Date: November 15, 1962
Creator: Hadley, J. W.
Partner: UNT Libraries Government Documents Department
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Criteria of the Post-Operative Cells, E-MAD Facility

Description: The purpose of this report is to present information on the design requirements of the post-operative cells at the E-MAD facility. It contains our reference operation plan, requirements for the post-operative cells, the cell service area, the warm machine shop and the manipulator repair area. This report is based on the best information presently available. The reference operation plan will be changed, as required, to be compatible with the E-MAD final design and the final design of the reactor. more
Date: October 15, 1962
Partner: UNT Libraries Government Documents Department
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THE DEVELOPMENT OF A SUMP-TYPE SOLIDIFIED-METAL SEAL

Description: A solidified-metal seal for possible use in moIten-saIt systems was fabricated and tested on a laboratory scale/su The seal consisted of an 80 Au-20 Cu (wt%) sealant alloy in contact with IN0R-8 base metal/su Eleven successive helium-leak-tlght sealings were effected before termination of the test due to a leak in one of the mating parts/su With better control over the heating cycle and slight modifications in seal design, it is expected that the useful life of a seal of this type could be exte… more
Date: March 15, 1962
Creator: Donnelly, R.G.
Partner: UNT Libraries Government Documents Department
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Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: July 1962

Description: This is the twenty-third progress report containing progress made in conducting the stress rupture, creep, and tensile tests in air and helium, stainless steel fatigue tests, and rupture, tensile, and creep tests with stainless steel.
Date: August 15, 1962
Creator: Andrews, R. C.; Barker, K. R. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
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Emission Characteristics of Tantalum, Tungsten, Rhenium, and Iridium in Plasma Diodes

Description: Experimental determinations of the ionic and electronic emission characteristics of Ta, W, Re, and lr cathodes in vapor thermionic converters are compared. It is shown that Ta provides superior thermal ionization qualities at high pressure compared with W, Re, and Lr. High electronic current densities may be obtained from Cs on Re and Cs on Ir at much lower Cs vapor pressures than from Ta or W. An over-all efficiency of 19% was achieved with a Re cathode at 2440 deg K. (auth)
Date: March 15, 1962
Creator: Gust, W. H.
Partner: UNT Libraries Government Documents Department
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Evaluation of the Blake Sodium Resistivity Meter

Description: Report issued by the APDA over an evaluation of the toroid sodium resistivity meter. Studies were conducted on carbon and oxygen contamination. As stated in the introduction, "the meter was also subjected to extensive testing in which variations in temperature, flow rate, and supply voltage were made in order to determine signal stability and effective range" (p. 5). This report includes tables, illustrations, and photographs.
Date: October 15, 1962
Creator: Atomic Power Development Associates
Partner: UNT Libraries Government Documents Department
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Expanded form of magnetic field with median plane

Description: An effort is made to supply an easily applied formulation of the expanded form of a magnetic field with a median plane. The coefficients up to the 6th degree terms in x and y are explicitly given. (PMA)
Date: December 15, 1962
Creator: Teng, L. C.
Partner: UNT Libraries Government Documents Department
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Experimental Studies of Transient Effects in Fast Reactor Fuels

Description: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F.… more
Date: November 15, 1962
Creator: Field, J. H.
Partner: UNT Libraries Government Documents Department
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Experimental Studies of Transient Effects in Fast Reactor Fuels. Series I. UO$sub 2$ Irradiations

Description: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO/sub 2/ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 … more
Date: November 15, 1962
Creator: Field, J. H.
Partner: UNT Libraries Government Documents Department
open access

Fabrication of Ceramic Internal Reflector for the SNAP 8 Experimental Reactor

Description: Fabrication of internal reflector pieces for the SNAP-8 core is described. These reflectors were made of BeO, with and without the addition of Sm/sub 2/O/sub 3/ as a nuclear poison. Because of the high density and dimensional tolerance requirements, the complexity of shapes, and the comparatively modest number of parts to be produced (approximately 1000), the blanks were hot pressed and subsequently machined with diamond wheels and cores. In almost all cases, the specified density of 98% of the… more
Date: July 15, 1962
Creator: Langrod, K.
Partner: UNT Libraries Government Documents Department
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