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Description: Engineering Metallurgy. Investigations were made on the following: development programs for Experimental Breeder Reactor No. 2 (EBR-II); fabrication of care and blanket components for Argonne Fast Source Reactor (AFSR); fabrication of spiked fuel rods for Experimental Boiling Water Reactor (EBWR) (Core lA); fuel for Transient Test Reactor Facility (TREAT); fuel elements for Experimental Breeder Reactor No. 1 (EBR-I) (Mark-IV); canning of plutonium loading for Zero Power Reactor No. 3 (ZPR-III); development of ceramic fuel materials; irradiation evaluations of various experimental fuel and control-rod materials: postirradiation examinations of full-scale reactor fuel elements: development of corrosion-resistant fuel and jacketing materials; nondestructive testing developments; and metallurgical assistance to the Fast Reactor Safety Program. Basic Metallurgy. Investigations were made on the following: preparation of high-purity materials; physical metallurgy of uranium; constitution and properties of uranium and plutonium alloys; alloying properties; x-ray and neutron-diffraction studies; problems in metal physics; corrosion research; irradiation effects; and ceramicmaterials research. (W.L.H.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department


Description: aqueous thorium oxide slurries have arisen in connection with the design of the lower portion of the blanket pressure vessel and its associated piping. The literaiure review on the angle of repose of various dry solids by Mrs. B. S. Neumann in J. J. Hermans' book on''Flow Properties of Dispersed Systems'' is summarized. Mrs. Neumann points out that both a dynamic and static angle of repose have been observed with the angles for dynamic systems being larger than for static systems. Results are reported for two different types of experiments with slurry discharged from run 200A-14 which gave static angles of repose of 45 to 50 deg and dynamic angles of 65 to 75 deg . (auth)
Date: February 14, 1958
Creator: Thomas, D.G.
Partner: UNT Libraries Government Documents Department

Studies of fusion reactor blankets with minimum radioactive inventory and with tritium breeding in solid lithium compounds: a preliminary report

Description: The feasibility of fusion reactor blankets with low residual activity is examined. Several designs are examined with regard to activation, tritium breeding ratio, mechanical design, tritium removal from the blanket, and thermal cycle efflciency. Using aluminum (SAP) as a structural material, it should be possible to build CTR blankets with ~10 curies/MW(e) of long-lived (half life one day or greater) residual activity (other than tritium), which is many orders of magnitude less than with Nb or stainless steel blankets. In the designs examined in this study, tritium is bred in -solid-lithium-containing materials, e.g., LiAl alloy, which have high-equilibrium tritium pressures. The tritium diffuses into either the helium-coolant stream, from which it is removed by absorption, or into the vacuum region between the first wall and plasma. Depending on processing methods and blanket parameters, the tritium blanket inventory should range from 10/sup 2/ to 10/sup 3/ curies/ MW(e). Tritium breeding ratios range from 0.9 to 1.5 depending on blanket design, while therrnal cycle efficiency is estimated to range from 35% to well over 40%, depending on design. Several module designs are developed in which helium-coolant exit temperatures are substantially above the operating temperature limit (~400 deg C) for the aluminum (SAP) structure. (auth)
Date: June 1, 1973
Creator: Powell, J.R.; Miles, F.T.; Aronson, A. & Winsche, W.E.
Partner: UNT Libraries Government Documents Department


Description: A method for removing sodium from fuel and blanket subassemblies that have been irradiated in the Enrico Fermi Atomic Power Plant reactor is described. In this method, the subassemblies are flushed with white oil aided by ultrasonic agitation, and the sodium is carried away from the surfaces of the subassemblies by the oil. Data gathered from experimental studies of the method are described; conceptual flow diagrams, materials balance sheets and equipment arrangements applicable to the Fermi plant are discussed; and sodium cleaning methods currently used are summarized. (D.L.C.)
Date: March 1, 1961
Creator: Kanaan, Z.R. & Nash, C.R.
Partner: UNT Libraries Government Documents Department


Description: A summary is presented of the information developed to date on the core and blanket fuel materials for the Fermi Fast Breeder Reactor. The specification requiremente for the core and blanket subassembly fabrication are discussed, along with special materials accountability and shipping problems. (W.L.H.)
Date: January 1, 1958
Creator: Ladd, C.M.; Hennig, R.J.; Homeister, O.E.; Leeser, D.O.; MacLeod, R.A.; Rateick, R.G. et al.
Partner: UNT Libraries Government Documents Department