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New K Reactor aluminum HCR: Temperature study

Description: Recent (HCR) Horizonal Control Rod operating problems at the K Reactors, caused primarily by graphite stack distortion, have stimulated several designs of HCR`s capable of operating under adverse conditions. One such design is an aluminum HCR, not completely dissimilar to the present HCR`s, conceived by the Research and Engineering Operation of I.P.D. The successful use of aluminum as a structural material is strongly dependent upon the operating temperature of the aluminum. This study was cond… more
Date: February 17, 1964
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Study of EOCR Modifications for Testing Fast Reactor Fuels

Description: Report issued by the APDA over studies conducted on "methods for increasing the power generation in a fast reactor fuel element test sample" (p. 9). The methods investigated are presented and discussed. This report includes tables, and illustrations.
Date: February 17, 1964
Creator: Ball, G.; DeFelice, J.; Edwards, J. J.; Jens, W. H.; Kovac, L. R.; Poggi, R. et al.
Partner: UNT Libraries Government Documents Department
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The Y-Nd and Sc-Nd Phase Systems

Description: Technical report. From Introduction : "In a recent study by Spedding, et al. on some rare earth alloy systems, an intermediate phase was found to form when a light rare earth (ABAC stacking) was alloyed with a heavy rare earth (ABAC stacking). This intermediate phase was found to have the structure of samarium metal with the stacking ABABCBCAC and was designated "delta". Since the cause of this rather unusual structure occurring in either samarium metal or these alloys is not known the study of… more
Date: February 1964
Creator: Beaudry, B. J.; Michel, M.; Daane, A. H. & Spedding, F. H.
Partner: UNT Libraries Government Documents Department
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SRE CORE III FUEL ELEMENTS THERMAL ANALYSIS

Description: The initial 30-Mw SRE Core III loading will contain a total of 33 fuel elements. Of these, the central 7 fuel elements are test elements and the remaining 26 are driver elements; 4 of the 7 test elements are designated as standard test elements. These elements are identical to the driver elements with the exception of the active fuel length. The remaining 3 test elements are designated as special test elements and incorporate fuel rods of smaller diameter and increased enrichment to obtain high… more
Date: February 27, 1964
Creator: Bergonzoli, F.
Partner: UNT Libraries Government Documents Department
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THEORY OF THE FIREBALL

Description: No Description Available.
Date: February 1, 1964
Creator: Bethe, H. A.
Partner: UNT Libraries Government Documents Department
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OUTGASSING BEHAVIOR OF EGCR MODERATOR GRAPHITE

Description: The outgassing characteristics of specimens of the EGCR moderator graphite stock were determined in vacuo to a maximum temperature of 1000 deg C using external resistance heating and to 1800 deg C by induction heating. The specimens examined were cut from several locations in two of the 18-in. x 18-in. x 20-ft graphite bars which had been prepared under fabrication conditions comparable to those used for the graphite columns present in the Experimental Gas- Cooled Reactor. Data are given which … more
Date: February 1, 1964
Creator: Blakely, J.P. & Overholser, L.G.
Partner: UNT Libraries Government Documents Department
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Progress report on NASA cermet studies identification SNC-12, January 1964

Description: This report details progress in an intensive investigation which was launched to determine the basic mechanisms leading to gross loss of UO{sub 2} fuel upon thermal cycling of UO{sub 2}-W cermets and to suggest means of overcoming this serious operational problem. (This problem was recently uncovered at both Lewis Research Center and at Hanford). More than 40 separate experiments were conducted in four high temperature furnaces, at temperatures to 2600 C, pressures from 10{sup {minus}5} mm vacu… more
Date: February 13, 1964
Creator: Cadwell, J. J.
Partner: UNT Libraries Government Documents Department
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Preoperational Power Stability Analysis of the Consumers Big Rock Point Plant

Description: Summary: An analytical study of the stability of the Big Rock Nuclear Reactor has been performed for the plant as built, and supplements a previous design stability study. The plant has been determined by this analysis to be very stable under every mode of operation anticipated during Phase I of the development program testing. Even under conservative assumptions of system parameters the minimum calculated gain and phase margins do not go below 13.0 db and 46 degrees, respectively. (Nor are … more
Date: February 1964
Creator: Case, J. M.
Partner: UNT Libraries Government Documents Department
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Temperature measurement systems

Description: No Description Available.
Date: February 1, 1964
Creator: Chandon, H.C.
Partner: UNT Libraries Government Documents Department
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Final report B, D, F reactor side shield hole boring technology

Description: Four years of intermittent development has culminated in the successful test drilling on-reactor, of one step plug hole. Since 1960, several different drive units and many diamond, carbide, and tool steel cutting heads were tried unsuccessfully in attempts to bore a stepped hole in a mockup of B, D, P side shielding. Success was finally achieved in 1963 using a standard horizontal boring mill and tool steel cutters. With slight modifications, this same equipment was successfully used in an on-r… more
Date: February 3, 1964
Creator: Clemans, W. H.
Partner: UNT Libraries Government Documents Department
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Reduction of Plutonium Compounds to Plutonium Metal

Description: A survey was made of the literature which was published on the reduction of plutonium compounds to plutonium metal between 1950 and April 1963. This report is a summary of the information which was gathered during the survey. (auth)
Date: February 1, 1964
Creator: Conner, W. V.
Partner: UNT Libraries Government Documents Department
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Internal graphite moderator forces study supplemental information

Description: This report discusses comments received on the previous report on internal graphite moderator forces (HW-79120); sleeve test channel inspection; and BDF reactor distortion.
Date: February 14, 1964
Creator: Cooley, D. E.
Partner: UNT Libraries Government Documents Department
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Stress Analysis of Specimens for in-Pile Creep Tests of Parabolic Graphite Beams

Description: The irradiation-induced creep of graphite is being investigated in experiments that consist of loading parabolically shaped cantilever beams at the free end and measuring the resulting deflections with time. A series of stress analyses was made to verify the applicability of the elementary strength-of- materials approach for obtaining relations between stress and creep strain from the load-deflection data. The results of the analyses, which included a theory- of-elasticity solution, an evaluati… more
Date: February 1, 1964
Creator: Corum, J. M.
Partner: UNT Libraries Government Documents Department
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The Development of Uranium Carbide as a Nuclear Fuel: Final Report

Description: From introduction: This is the final report on uranium carbide studies sponsored by the United States Atomic Energy Commission and performed by United Nuclear Corporation at its New Haven Research Laboratories during the period from May 1959 to January 1964. The work was part of the Commission's Fuel Cycle Development Program aimed at lowering the cost of nuclear power by improving fuel cycle technology. At the inception of this program in 1959, some work was in progress on uranium carbide. Lit… more
Date: February 29, 1964
Creator: Crane, J. & Gordon, E.
Partner: UNT Libraries Government Documents Department
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Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity

Description: Abstract: The question of how crack-free, protective oxide films can form on zirconium during oxidation when the Pilling-Bedworth ratio is about 1.5 has been considered by a study of the relative plasticity of various forms of zirconia. Hot hardness measurements showed that doping mono-clinic zirconia with iron, nickel, or chromium resulted in softer (more plastic) structures and that yttrium additions slightly reduced the plasticity. Calcia-stabilized cubic zirconia was found to be more pla… more
Date: February 20, 1964
Creator: Douglass, D. L. (David Leslie), 1931-
Partner: UNT Libraries Government Documents Department
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THERMAL ANALYSIS OF AN ANODIZED REFLECTOR FOR SNAP-2

Description: Anodization of the SNAP reflector for the 125 kw, 1300 deg F design point results in a reflector temperature of 760 deg F. By comparison the reflector temperature for the 53 kw, 1200 deg F design point with no anodization was 795 deg F. (auth)
Date: February 18, 1964
Creator: Dufoe, G.E.
Partner: UNT Libraries Government Documents Department
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