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Aerial Radiological Monitoring System: [Part] 1. Theoretical Analysis, Design, and Operation of a Revised System

Description: Report containing an analysis of the Aerial Radiological Monitoring Survey (ARMS) program detailing the feasibility of improvements. Includes suggestions for revisions of the existing ARMS system.
Date: July 1960
Creator: Merian, R. F.; Lackey, J. G. & Hand, J. E.
Partner: UNT Libraries Government Documents Department
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ART-04--a Modification of the Art Program for the Treatment of Reactor Thermal Transients on the IBM-704

Description: Several recent modifications of the ART program for the study of the behavior of a nuclear reactor during various thermal transients are described. The program requires a 32,000-word IBM-704 computer with six tape units. The major modifications are provision for a slip flow model and for void reactivity contribution. (auth)
Date: July 1960
Creator: Meyer, J. E. & Peterson, W. D.
Partner: UNT Libraries Government Documents Department
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Catalog of North Texas State College: 1960-1961, Graduate

Description: Catalog for North Texas State College includes information about class offerings as well as general information about the school (academic calendar, list of officers and faculty, admissions and degree requirements, financial information, etc.).
Date: July 1960
Creator: North Texas State College
Partner: UNT Libraries Special Collections
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Cesium-137 In Milk

Description: Samples of liquid milk from Bombay and 27 other stations in India, and imported powder milk from Australia, Denmark, Holland, U.K. and United States have been measured for their cesium-137 and potassium-40 contents.
Date: July 1960
Creator: Vohra, K. G.; Bhatnagar, V. S.; Mishna, U. C. & Ragupathy, S.
Partner: UNT Libraries Government Documents Department
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CHEMICAL DECONTAMINATION OF THE ANL-2 HIGH-PRESSURE WATER LOOP

Description: The chemical decontamination of the ANL-2 Highpressure Water Loop at the MTR is described. A mixture of sodium hydroxide and potassium permanganate was first applied to oxidize partially and loosen the magnetite corrosion film on the loop surfaces. Next, the system was treated with a solution of Versenol 120 to remove and suspend the loosened oxide film. The third chemical treatment was a mixture of sulfamic acid, HEDTA, hydrazine, and Rodine 80. After the first two chemical treatments a brown … more
Date: July 1, 1960
Creator: Crothers, C.C.
Partner: UNT Libraries Government Documents Department
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COHERENT ELECTROMAGNETIC EFFECTS IN HIGH-CURRENT PARTICLE ACCELERATORS: I. INTERACTION OF A PARTICLE BEAM WITH AN EXTERNALLY DRIVEN RADIO-FREQUENCY CAVITY

Description: A calculation is made of the interaction of a beam of particles in an accelerator with the radio-frequency cavity that provides the accelerating mechanism of the machine. A Hamiltonian for synchrotron motion is employed that makes possible the simultaneous solution of Maxwell's equations and the Vlasov equation, so that a self-consistent distribution of particles in synchrotron phase space is determined. The effective voltage on the cavity due to the beam of charged particles is of the order of… more
Date: July 1, 1960
Creator: Neil, V. Kelvin & Sessler, Andrew M.
Partner: UNT Libraries Government Documents Department
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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments With Oxide Fuel Pins

Description: Critical experiments with pin-type oxide fuel elements for the CETR are described. These experiments were conducted to provide data on the infinite medium properties of the lattice inside the canned elements in the various CETR loading zones and to obtain specific information on the fullsize CETR core. Measurements are described and results are interpreted. (J.R.D.)
Date: July 1, 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor-Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods. (J.R.D.)
Date: July 1, 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.
Date: July 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Partner: UNT Libraries Government Documents Department
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Control Blade Worth by Partial Water Height and Soluble Boron Methods

Description: The series of experiments described in this paper was performed to determine reactivity values of various patterns of fully inserted cruciform control blades. The experiments yielded the worth of fully inserted blade patterns in terms of their holddown characteristics.
Date: July 1960
Creator: MacKinney, Arland L. & Ball, Russell M.
Partner: UNT Libraries Government Documents Department
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CORROSION OF STAINLESS STEEL IN HNO$sub 3$-HF SOLUTIONS

Description: Studies were made on the safe handling of HHO/sub 3/-HF solutions in 304 L and 309SCb stainless-steel equipment under carefully controlled conditions. The corrosion behavior of both wrought and welded 304L and 309SCb was investigated in various HNO/sub 3/--HF solutions, ranging in HNO/sub 3/ concentration from 0 to 10.0 M and HF concentration from 0.01 to 1.5 M, at temperatures from 24 deg C to the boiling point. (auth)
Date: July 1, 1960
Creator: Kranzlein, P.M.
Partner: UNT Libraries Government Documents Department
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Cost Study of a 100-Mw(E) Direct-Cycle Boiling Water Reactor Plant

Description: A technical and economic evaluation is presented of a direct-cycle light- water boiling reactor designed for natural circulation and internal steam-water separation. The reference lOO-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. (W.D.M.)
Date: July 1, 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

Description: Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date: July 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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COULOMETRIC TITRATION OF URANIUM IN NITRIC ACID SOLUTIONS

Description: A coulometric titration method was developed for the determination of uranium in HNO/sub 3/ solutions. Uranium was reduced to the (IV) state and was titrated with electrolytically generated cerium(IV). The colorimetric end point was detected automatically by a photometric technique. Interference from nitrate was eliminated by the addition of urea to the titration medium. The coefficient of variation for the analysis of uranium was 3.2% for 1-mg samples and 0.3% for 100-mg samples. With the addi… more
Date: July 1, 1960
Creator: Fulda, M.O.
Partner: UNT Libraries Government Documents Department
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Critical Tests for PRT Reactor

Description: This document authorizes the performance in accordance with the specifications noted, the PRTR Critical Tests described herein. The experiments described have the following objectives:
Date: July 1, 1960
Creator: Triplett, J. R.; Anderson, J. K.; Peterson, R. E.; Regimball, J. J.; Russell, J. T.; Schmid, L. C. et al.
Partner: UNT Libraries Government Documents Department

[Drawings for legal sales]

Description: Photograph of two drawings for the vote for legal sales. The top drawing is of a man in a suit holding a stack of papers in one hand and holding the other hand over his arm. There is also a pair of glasses on a table in front of him, and the statue of liberty behind him to the right. The bottom drawing is of a man standing and pointing at a line graph, as another man sitting beside him watches.
Date: July 1, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections

[Drawings for vote]

Description: Photograph of two drawings about the vote for legal sales. The top one is of a man standing with his arms up, as another person in front of him is pointing a gun at him as they hold money in their other hand. The writing below the drawing says, "Vote for legal sales - Saturday, July 9th." The drawing below this is of a man working in a factory, with a wide shot of said factory shown on the right of him. The same writing is also below this image.
Date: July 1, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections

[Drug store slide]

Description: Photograph of a slide that says, "Jack Collier and serval drug stores." It is written in simple, black font on a white background.
Date: July 1, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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Effects of Irradiation on the EBWR Fuel Alloy Uranium-5 w/o Zirconium-1.5 w/ o Niobium. Final Report-Metallurgy Program 6.1.20

Description: Irradiations were made on small specimens of U-5 wt.% Zr-1.5 wt.% Nb alloy with a wide variety of fabrication histories and heat treatments in order to determine the optimum heat treatment for the fuel plates for the Experimental Boiling Water Reactor (EBW). In the time available, a heat treatment could not be found which simultaneously conferred dimensional stability and corrosion resistance to the alloy. The most effective heat treatment for dimensionally stabilizing swaged or round-rolled ma… more
Date: July 1, 1960
Creator: Kittel, J. H.
Partner: UNT Libraries Government Documents Department
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