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Storm Data and Unusual Weather Phenomena, Volume 3, Number 6, June 1961

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: August 1, 1961
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
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Space Programs Summary 37-10, Volume 1: For the Period May 1, 1961 to July 1, 1961

Description: Bimonthly report presenting a review of engineering and scientific work performed, or managed by the Jet Propulsion Laboratory (JPL) for the National Aeronautics and Space Administration during a two-month period. This volume presents details of the lunar program (Ranger), the planetary-interplanetary program (Mariner), and the deep space instrumentation facility.
Date: August 1, 1961
Creator: Jet Propulsion Laboratory (U.S.)
Partner: UNT Libraries Government Documents Department
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Waste Treatment and Disposal Progress Report for April and May1961

Description: Progress is reported on developments in waste treatment and disposal in terms of: high-level-waste calcination; low-level-waste treatment; engineering, economics, and hazards evaluation; disposal in deep wells; disposal in natural salt formations; Clinch River studies; fundamental studies of minerals; and White Oak Creek Basin study.
Date: August 1, 1961
Creator: Blanco, R. E. (Raymond Eugene), 1918-1987 & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Speed-of-control limits, 105-DR

Description: The current operating conditions at 105-DR, because of the recent Ball 3X drop, dictate temporary lower speed-of-control limits. While is si still not expected that this reactor will be limited by the speed-of- control criterion, it is felt that the limit curves have been temporarily sufficiently reduced as to warrant publication of former limits. Limit curves as a function of weighted graphite temperature for the continuous and block discharge schemes are included in this document. The two sou… more
Date: August 1, 1961
Creator: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Coextrusion Process Specifications

Description: These specifications, prepared for the N-reactor fuel, provide the framework on which the overall control and guidance of the manufacturing process shall be built.
Date: August 1, 1961
Partner: UNT Libraries Government Documents Department
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The Coefficient of Volume Expansion for Water and Water Vapor in the Critical Region. Technical Report No. 6

Description: A tabulation is presented of the coefficients of volume expansion for water and for water vapor along eleven isobars in the critical region encompassed by pressures from 3000 to 4000 psia and temperatures from 690 to 750 deg F. Graphical techniques were employed to derive these values from precise P-V-T data. The over-all error in the derived values of the volume expansion coefficient was estimated to be within 5%. However, in the region of maximum values for the coefficient of volume expansion… more
Date: August 1, 1961
Creator: Nowak, E. S. & Grosh, R. J.
Partner: UNT Libraries Government Documents Department
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Hydrogen Distribution and Leak Rate From the Reactor Coolant System. Test Evaluation-RNI-31A

Description: Hydrogen is injected into the coolant to a concentration of about 60 cc/ kg. The decrease in H concentration is measured as a function of time, and of the point of addition. The H may be added at the inlet or outlet sides of eithe: of two ion exchangers. The decontamination factors of these ion exchangers are not affected by the presence of the H. The time required for the H concentration to drop to half its original value varies between 118 and 172 hr. (T.F.H.)
Date: August 1, 1961
Partner: UNT Libraries Government Documents Department
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Process Vessel Design for Frozen-Wall Containment of Fused Salt

Description: The feasibility of the containment of a molten sodium fluoride- zirconium fluoride salt at 550 deg C in vessels with a protective inner liner of frozen salt of the same composition was demonstrated. Two different designs were used for supplying internal heat directly to the molten salt: induction heating and electrolytic heating. The test equipment was of a size practical for processing zirconiumuranium alloy reactor fuel by the Fused Salt Process. (auth)
Date: August 1, 1961
Creator: Kessie, R. W.; Gabor, J. D.; Mecham, W. J. & Jonke, A. A.
Partner: UNT Libraries Government Documents Department
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Status Report No. 1 on Clinch River Study

Description: A study of the Clinch River below Oak Ridge National Laboratory was initiated in Feb. 1960 to obtain fundamental information on the physical, chemical, and biological dy namics of this fresh-water stream which receives large volumes of low-level radioactive wastes. The fate of radioactive materials discharged to the river, the mechanisms of dispersion of radionuclides released to the river, the direct and indirect hazards of current disposal practice in the river, and the over-all usefulness of… more
Date: August 1, 1961
Creator: Morton, R.J. ed.
Partner: UNT Libraries Government Documents Department
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PREPARATION OF ALLOY FOR FIRST CORE LOADING OF EBR-II

Description: The alloy used for the fabrication of the fuel pins for the first core loading of the second Experimental Breeder Reactor (EBR-II) was prepared in the prototype equipment developed for the melt-refining processing of the irradiated EBR-II fuel. One hundred and twenty-five 10-kg ingots were made, of which 40 were unenriched uranium-fissium alloy and 85 were enriched uranium-fissium alloy. In addition, nineteen 10-kg batches of unenriched uranium-fissium scrap and forty- seven 10-kg batches of en… more
Date: August 1, 1961
Creator: Hampson, D.C.
Partner: UNT Libraries Government Documents Department
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Annotated Bibliography of Theories of the Equation of State of Ionized Gases and Strong Electrolyte Solutions

Description: This bibliography lists 297 references on the equation of state of ionized gases and electrolyte solutions, including calculations of closely related quantities such as free energy, partition functions, o smotic pre ssure, activity coefficients, and equilibrium compositions of partially ionized systems. A subject index and a supplementary list of 42 bibliographies on plasma physics and similar topics are included. (auth)
Date: August 1, 1961
Creator: Brush, S. G. & Wensrich, C. J.
Partner: UNT Libraries Government Documents Department
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Development of a Ti-Al-Cb Alloy for Use at 1200-1800 F

Description: >Titanium-base alloys containing major amounts of Nb and Al are being studied to develop new high-temperature alloys of low density. Findings derived from the preparation and examination of quaternary alloys containing small additions of Sn, Hf, or Zr; high-purity ternary alloys, and ten-pound melts of Ti-l5Nb-10A1 and Ti-l7.SNb-l5Al are presented. In a number of alloys, improved tensile properties and oxidation resistance resulted from the addition of Sn, Hf, or Zr, and in some instances very … more
Date: August 1, 1961
Creator: McAndrew, J. B. & Simcoe, C. R.
Partner: UNT Libraries Government Documents Department
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REACTOR LABORATORY EXPERIMENTS

Description: An exposition is presented comprising a basic set of experiments in reactor physics, engineering, and technology developed by the International Institute of Nuclear Science and Engineering. Twenty-two experiments are included in a program which may be divided into groups associated with the Argonaut Reactor, the AGN-201 Reactor, and with other reactors or auxiliary equipment. (J.R.D.)
Date: August 1, 1961
Creator: Sturm, W.J. ed.
Partner: UNT Libraries Government Documents Department
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ISOMERIC CROSS-SECTION RATIOS FOR SOME (n,$gamma$) AND (/cap alpha/,XN) REACTIONS

Description: Isomeric cross section ratios for several nuclear reactions in the medium mass region were measured. The cross section ratios of isomers produced by the thermal neutron irradiation of Se/sup 60/, Rh/sup 103/, Pd/sup 106/ TE/sup 128/ and Cs/s up 133/ were measured. Isomeric cross section ratios for the formation of the isomeric pair In/sup 110/ and In/sup 110m/, produced in the Ag/ sup 107/ ( alpha ,n) and the Ag/sup 109/ ( alpha ,3n) reactions were also measured at several energies of the incom… more
Date: August 1, 1961
Creator: Bishop, Carl T.
Partner: UNT Libraries Government Documents Department
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Remote Plastic Bag Passout Unit for High-Level Radiochemical Operations

Description: A system is designed for making remote sealed-bag passouts from a multicurie-level chemistry processing enclosure. The polyethylene bags are changed remotely without exposing contaminated surfaces while always maintaining a low leak rate seal. The system employs an interchange box (passout box) attached to the chemistry enclosure. Integrated with the box is a hydraulically operated jack that raises and lowers the bags, and a welder-cutter for sealing them. A single master-slave manipulator team… more
Date: August 1, 1961
Creator: Fleischer, E. S.; Parsons, T. C. & Howe, P. W.
Partner: UNT Libraries Government Documents Department
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MAGNETIC FIELD MEASUREMENTS IN A CYLINDRICAL PINCH TUBE

Description: Magnetic field measurements in a cylindrical linear pinch tube with probes are described. Tests are performed with a discharge current frequency of 20 kilocycles in nitrogen at an initial pressure of 0.1 mm Hg. Initial capacitor voltage is varied from 1000 to 5000 volts. The magnetic field distribution, the radial current distribution, and the current density in the pinch tube are described. The discharges are concluded to be symmetric above 2000 volts. The symmetric discharges have distinct ch… more
Date: August 1, 1961
Creator: Donner, T. & Aronowitz, L.
Partner: UNT Libraries Government Documents Department
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Bobcat (Program No. 56) Code Preparation Analysis on the IBM-650

Description: The BOBCAT code that is programmed for the IBM650 is described. The code facilitates the nuclear analysis of APPR-type cores by performing many of the routine calculations necessary to obtain input to various IBM-650 and IBM-704 codes. Using fuel element geometry and U/sup 235/ and B/sup 10/ loadings as input, the code prepares input to the MUFT-III and various P/sub 3/ codes as output; in addition, a large amount of detailed descriptive core data that is useful in nuclear analysis calculations… more
Date: August 1, 1961
Creator: Bobe, P. E. & Caton, R. L.
Partner: UNT Libraries Government Documents Department
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An Experimental Investigation of High-Flux Free Convection Heat Transfer to Water Up to Near-Critical Conditions

Description: An investigation was made to increase the basic knowledge of nucleate and film boiling heat transfer to fluids up to their critical pressures. An extensive literature survey of the subject indicated a scarcity of consistent data and an absence of proven methods for analysis. This situation led to the design and construction of experimental apparatus suitable for measuring rates of free convection heat transfer and associated temperature differences for fluid conditions up to 4000 psi and 800 de… more
Date: August 1, 1961
Creator: Holt, V. E.
Partner: UNT Libraries Government Documents Department
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Dimensional Behavior of the Experimental Gas-Cooled Reactor Fuel Element at Elevated Temperatures

Description: The Experimental Gas-Cooled Reactor (EGCR) fuel assemblies consist of a cluster of seven fuel elements contained in a graphite sleeve. Each element is composed of hollow cylindrical UO/sub 2/ pellets encapsulated in a type 304 stainless steel tube. The dimensional behavior of the fuel element was determined in an apparatus which simulated the thermal conditions predicted for the EGCR. Particular emphasis was placed on determining the relationship between the fuel temperature and axial expansion… more
Date: August 1, 1961
Creator: Martin, W. R. & Weir, J. R.
Partner: UNT Libraries Government Documents Department
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