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Salt Bath Heat Transfer Rates for Uranium Plate

Description: Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date: February 1, 1962
Creator: Burditt, R. B.
Partner: UNT Libraries Government Documents Department
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Development of Ductile Beryllium Composites

Description: The work of the second year to produce ductile beryllium composites by liquid-phase sintering is reported. Ductility in a predominantly beryllium composite was sought through the attainment of a structure in which beryllium particles are enveloped in a ductile metallic matrix. As the result of the investigation of aluminum-silver binary al!oys, aluminum-40 to 50% silver compositions were added to the silver-5 to 8% aluminum compositions as candidate matrices satisfying the requirenent that the … more
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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Secondary Missiles Generated by Nuclear-Produced Blast Waves

Description: The generation of secondary missiles by blast waves was investigated in Operation Plumbbob for three nuclear detonations with estimated yields of 11, 38, and 44.5 kt. A trapping technique was used to determine the impact velocities for 17,524 missiles (stones, glass fragments, spheres, and military debris or steel fragments) which occurred in open areas, houses, and an underground shelter with an open entryway. The equivalent ideal-wave peak overpressures computed from measured blast data for t… more
Date: February 1, 1962
Creator: Bowen, I. G.; Franklin, M. E.; Fletcher, E. R. & Albright, R. W.
Partner: UNT Libraries Government Documents Department
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Shield capsule thermal analysis

Description: No Description Available.
Date: February 1, 1962
Creator: Pugliese, D.A.
Partner: UNT Libraries Government Documents Department
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Final summary of impurities in beryllium oxide as used in the Tory II-A-1 reactor. Pluto technical note No. 257

Description: Declassified 26 Nov 1973.<><DSN>29:020150<ABS>has resulted from a sophisticated consideration of its application as a ramjet engine. An idealized reactor power profile was derived directed toward optimizing the transfer of heat energy to the airstream. Some twenty-six classes of fueled tubes have been used to tailor both axial and radial reactor power profiles accordingly. Procedures for the fabrication of components and assembly of the reactor have consequently become tedious and lengthy to sa… more
Date: February 1, 1962
Creator: Hampel, V. E. & Moran, W.
Partner: UNT Libraries Government Documents Department
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Thermal design of SNAP reactors

Description: No Description Available.
Date: February 1, 1962
Creator: Cohn, P.D.
Partner: UNT Libraries Government Documents Department
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The Effect of Graphite Chemical Reactivity on Thermal Instability Conditions in Air-Cooled Channels

Description: Conditions leading to thermal instability in air-cooled channels are mathematically expressed. It is shown that thermal instability occurs only if the air temperature approaches the graphite temperature. The length of channel necessary to yield a particular air temperature is derived. The effects of enhanced reactivities on the instability conditions are discussed. (R.J.S.)
Date: February 1, 1962
Creator: Schweitzer, D. G.
Partner: UNT Libraries Government Documents Department
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COUNTERCURRENT MUTUAL SEPARATION OF Y$sup 91$ AND Pm$sup 147$ BY SOLVENT EXTRACTION USING PULSE COLUMN

Description: The use of continuous solvent extraction was proved quite satisfactory in separating Y/sup 91/ from Pm/sup 147/, using synthetic mixtures of the nuclide pair on a tracer level. The separation was conducted in a compound perforated plate pulse column using a solvent containing 10% HDEHP, di(2 ethylhexyl) phosphoric acid, in toluene. Flow rates to the extraction column were maintained around 1 ml/min of feed, 3 ml/min scrub and 12 ml/min solvent giving one volume change per hour. Pulse frequency … more
Date: February 1, 1962
Creator: Mandil, M. A.; Mason, G. W. & Peppard, D. F.
Partner: UNT Libraries Government Documents Department
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A Fuel Reprocessing Plant for Fast Ceramic Reactors

Description: A study was made of the adaptation of the HAPO anion exchange process to the reprocessing of Fast Ceramic Reactor (FCR) fuel using the Idaho Small Plant Concept. It is shown that the anion exchange flowsheet meets the reprocessing objectives of the FCR case and can be adequately accommodated in the Small Plant Concept. Capacities of up to 1550 Md(e) are feasible in the Small Plant and unit reprocessing costs range from 0.14 to 0.28 mills/kwh depending on the number of reactors to be processed. … more
Date: February 1, 1962
Creator: Alter, H. W.
Partner: UNT Libraries Government Documents Department
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Efficiency of Multiple Traversal Targets

Description: The efficiency of multiple traversal targets is defined as the probability that a proton dies by making a nuclear collision in the target rather than by hitting the limit of the synchrotron aperture. The efficiencies of Be, Al, Cu, and Pb targets are shown for 15 and 30-Bev protons in the Brooknaven AGS. Beryllium was found to be the most efficient. (M.C.G.)
Date: February 1, 1962
Creator: Courant, E. D.
Partner: UNT Libraries Government Documents Department
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HYDROLOGIC AND GEOLOGIC STUDIES FOR PROJECT GNOME. Preliminary Report

Description: Geologic lnformation required to define the pre- and post-shot physical and chemical characteristics of the sait and other rocks affected by the exploslon was gathered. Information on the pre- and post-shot hydrologic condltlons at the site and the surrounding area was also obtalned. (M.C.G.)
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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Significance of Urine Uranium Excretion Data

Description: No Description Available.
Date: February 1, 1962
Creator: Lippmann, M.; Ong, Long D. Y. & Harris, William B.
Partner: UNT Libraries Government Documents Department
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Progress Report on Neutron Radiography

Description: BS> The potential advantages of neutron radiography as an inspection method are discussed along with a historical review and discussions of neutron sources and detectors. The results of the current investigation of neutron-image detectors are discussed in regard to photographic speed, relative neutron-gamma response, and resolution comparisons. Two neutron-image detecting methods are discussed. In one, the direct-exposure method, both the converter screens and the film are exposed to the neutro… more
Date: February 1, 1962
Creator: Berger, H. & McGonnagle, W.J.
Partner: UNT Libraries Government Documents Department
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TRANSPORT OF NOBLE GASES IN GRAPHITES. Progress Report for the Period January 31, 1961 to January 31, 1962

Description: A model was derived for the diffusion of gases in porous media in the absence of temperature and pressure gradients, in which portions of the medium are visualized as a collection of uniformly distributed dust'' particles (giant molecules) which are constrained to be stationary. Thus, it was possible to derive all the desired results from rigorous diffusion equations for multi- component mixtures. The results apply over the entire pressure range from the Knudsen region to the normal diffusion r… more
Date: February 1, 1962
Creator: Truitt, J.; Smith, N. V.; Watson, G. M.; Evans, R. B., Ill, & Mason, E. A.
Partner: UNT Libraries Government Documents Department
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COMPONENT FEASIBILITY TEST REPORT FOR THE AMF ON-POWER REFUELING SYSTEM FOR THE DOUGLAS POINT PLANT

Description: Activities in a phase of CANDU I refueling machine development are reported which are concerned with obtaining test data for various system subcomponent parts. The basis for selecting those units requiring test was established through engineering evaluation of available information. Results of tests based on these requirements are included in the form of test reports. (J.R.D.)
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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Determination of Radiation Contamination Levels During Core I, Seed 2-Seed 3 Refueling Operations. Test Evaluation (T-643128)

Description: A record is presented of radiation contamination levels observed in the work area during the Core I Seed 2-Seed 3 refueling operations. The radiation levels for Seed 2-3 refueling were somewhat higher thand those for Seed 1-2 refueling in certain areas and are ascribed to operations being carried out under dry conditions. Maximum contamination levels were also higher, but the general contamination level was lower. The activity of canal water was higher and characterization was made on some of t… more
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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Carbide Fuel Development. Progress Report, September 15, 1961 to December 31, 1961

Description: Single phase, solid solution, UC-PuC powder was synthesized reproducibly from a mixture of the oxides and carbon. A simple method of monitoring the reaction was developed. UC-PuC-0.1 wt% Ni pellets of 93% theoretical density were made reproducibly, with some samples as high as 95% of theoretical denstty. The pellets contain minor amounts of (U,Pu)/sub 2/C/sub 3/ most of the time. Efforts to make reproducible 95%, single-phase material are under way. Microprobe analysis of UC-0.1 wt% Ni specimen… more
Date: February 1, 1962
Creator: Strasser, A. & Taylor, K.
Partner: UNT Libraries Government Documents Department
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THE DISTORTED-WAVE THEORY OF DIRECT NUCLEAR REACTIONS. I. "ZERO-RANGE" FORMALISM WITHOUT SPIN-ORBIT COUPLING, AND THE CODE SALLY

Description: The distorted-wave theory of direct nuclear reactions is presented in a unified manner, in which the effects of assuming various reaction mechanisms and nuclear models appear only in certain radial form factors. The zero-range approximation is used, and spin-orbit coupling is neglected in the distorted waves. Formulas are given for transition amplitudes, cross sections, and polarizations. A description is given of the IBM-704 computer code SALLY that is based on these formulas. (auth)
Date: February 1, 1962
Creator: Bassel, R.H.; Drisko, R.M. & Satchler, G.R.
Partner: UNT Libraries Government Documents Department
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