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in subjects: "Beryllium Oxides"  
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EXPERIMENTAL ATTEMPTS TO STABILIZE A CUBIC FORM OF BeO

Description: Binary mixtures of BeO with the oxides Al/sub 2/O/sub 3/, CaO, Li/sub 2/ O, MgO, Sc/sub 2/O/sub 3/, TiO/sub 2/, Y/sub 2/O/sub 3/, and ZrO/sub 2/ were fired to temperatures in excess of 2050 deg C in an attempt to produce a stabilized cubic crystalline modification of BeO. No evidence was observed in microscopic and x-ray diffraction analyses of the cooled specimens that a cubic form of BeO had formed in the experiment. (auth)
Date: December 22, 1961
Creator: Thoma, R.E.; Friedman, H.A. & McVay, T.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MARITIME GAS-COOLED REACTOR PROGRAM. A REVIEW OF THE MARITIME GAS-COOLED REACTOR PROGRAM

Description: Presented at the Eleventh Professional Divisions Conference of the San Francisco Section of the American Society of Mechanical Engineers, Noveraber l6, l96l. The MGCR program and its objectives are discussed. The basic MGCR plant is described. The design of the Experimental Beryllium Oxide Reactor is also described. (M.C.G.)
Date: December 22, 1961
Creator: Trickett, K.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE EXPERIMENTAL BERYLLIUM OXIDE REACTOR. MARITIME GAS-COOLED REACTOR PROGRAM

Description: LIUM OXIDE REACTOR. MARITIME GAS-COOLED The Experimental Beryllium Oxide Reactor, EBOR, will be constructed at the National Reactor Testing Station as the AEC portion of the joint Maritime Administration--AEC Maritime Gas Cooled Reactor Program. The ultimate goal of the Program is the development of nuclear power plants employing a helium cooled and beryllium oxide moderated reactor directly coupled to a closed cycle gas turbine. The objective is to obtain compact nuclear engines suitable for u… more
Date: July 1, 1961
Creator: Moore, W.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Literature Survey of Gases in Beryllium. Report to Wright Air Development Division

Description: Structural and thermodynamic properties of beryllium, beryllium-oxygen systems, beryllium-nitrogen systems, and beryllium-hydrogen systems as determined by various researchers are surveyed. Diffusion properties, reaction kinetics, and vapor pressures are given where they were available. 44 references. (D.C.W.)
Date: January 17, 1961
Creator: Pemsler, J. P. & Anderson, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MOUND LABORATORY MONTHLY PROGRESS REPORT FOR JUNE 1961 ON CHEMISTRY

Description: Plastic Research. The tensile strength of Dacron-filled diallyl phthalate was determined to average 4377 psi. Composition and stress-strain data are tabulated for ten adhesive films. Analytical studies of an adhesive exudate are reported. Radioelements. Results of analysis of ioniumbearing raffinates and residues for Th/sup 232/ and of aged>s Ra/sup 223/ for Ac/sup 2/2/sup >/s7>s are given. Progress on Pa recovery from raffinates and residues and separation from Nb is reported. Isotope Separati… more
Date: June 30, 1961
Creator: Eichelberger, J.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AIRCRAFT NUCLEAR PROPULSION DEPARTMENT NUCLEAR SAFETY GUIDE

Description: The limitations and operating techniques which were in effect at ANPD for the prevention of criticality accidents are summarized. The standards followed by the atomic industry were followed; however, the safe mass of U/sup 235/ moderated with beryllium oxide and hydrogeneous materials was based upon criticality experiments conducted at ANPD. Although the guide was primarily for the use of the ANPD nuclear safety control organization, it may also be of assistance to designers and operating manag… more
Date: June 1, 1961
Creator: Pryor, W.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, October-December 1960

Description: ICPP Operations. Changes made in processing equipment are described, and the use of continuous steam stripping to free waste solvent of Pu is described. Agueous Processing Studies. Studies were made of methods for separating Zr from dissolver solutions of U-Zr alloys. Recovery of U from BeO/ sub 2/-UO/sub 2/ ceramic fuels by grinding-leaching technique using boiling HNO/ sub 3/ reached 75 to 80%. Waste Calcination. Test results of feed spray nozzles for use in the Demonstrational Waste Calcinin… more
Date: May 15, 1961
Creator: Bower, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SOME PROPERTIES OF BERYLLIUM OXIDE

Description: S>The primary objective of the literature search was to determine the best values for the properties involved in the thermal stress parameter. Comparison of data from various investigators indicates that thermal expansion of beryllia is independent of density. A wide variation was found in the thermal conductivity values of beryllia. Graphs and tables are presented which summarize and compare data from various sources. A bibliography of 53 references for some of the major items of the stress pa… more
Date: May 19, 1961
Creator: Lillie, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FAST-NEUTRON AND GAMMA SPECTRUM AND DOSE IN BERYLLIUM OXIDE

Description: Neutron and gamma penetrations through and behind BeO were measured. Neutron spectra measurements by threshold foil techniques indicated practically no change in the fast-neutron spectrum above 2.5 Mev in BeO. Thus, beryllium appears to lie in the transition region between the very light elements that harden a fission spectrum and the heavier elements that soften it. The ratio of fast-neutron fluxes below and above 2.5 Mev increased rapidly with distance through the BeO. Information indicated t… more
Date: January 11, 1961
Creator: Klingensmith, Raymond W.; Jung, Richard G.; Lindgren, William A.; Epstein, Harold M. & Chastain, Joel W., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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General Reactor Sizing Techniques. Volume I. Aerothermodynamic Optimization

Description: A method is presented for the aerothermodynamic optimization of the net power and/or propulsive thrust per unit reactor free flow area of a nuclear power plant operating on the Brayton cycle. A system so optimized will translate into the minimum size, therefore the minimum weight, nuclear system for any selection of reactor materials, lifetime, and fuel loading. The theory and development of the thermodynamic optimization process, the importance and effect of various parameters, and specific me… more
Date: June 1, 1961
Creator: Prickett, W. Z.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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