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The Abilene Reporter-News (Abilene, Tex.), Vol. 81, No. 12, Ed. 1 Saturday, July 1, 1961
Daily newspaper from Abilene, Texas that includes local, state, and national news along with advertising.
Date:
July 1, 1961
Creator:
unknown
Object Type:
Newspaper
System:
The Portal to Texas History
Airborne Gamma-Ray Spectrometer and Magnetometer Survey, Brainerd Quadrangle, Minnesota: Final Report, Volume 1
A report regarding an airborne gamma-ray spectrometer and magnetometer survey of the Brainerd Quadrangle, Minnesota
Date:
July 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
[Brainerd Quadrangle: Average Record Data Listings]
Average record data listings taken during aerial gamma-ray and magnetic surveys of the Brainerd quadrangle in Minnesota.
Date:
July 1961
Creator:
unknown
Object Type:
Dataset
System:
The UNT Digital Library
[Brainerd Quadrangle: Single Record Data Listings]
Single record data listings taken during aerial gamma-ray and magnetic surveys of the Brainerd quadrangle in Minnesota.
Date:
July 1961
Creator:
unknown
Object Type:
Dataset
System:
The UNT Digital Library
Bulletin of the Medical Department, Brookhaven National Laboratory (1961)
N/A
Date:
July 1, 1961
Creator:
Brookhaven National Laboratory
Object Type:
Report
System:
The UNT Digital Library
Catalog of Hardin-Simmons University, 1960-1961
Catalog describes the governance, history, admission requirements, course offerings, university calendar, and campus life of Hardin-Simmons University in Abilene, Texas.
Date:
July 1961
Creator:
Hardin-Simmons University
Object Type:
Book
System:
The Portal to Texas History
Catalog of North Texas State College: 1961-1962, Graduate
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 1961
Creator:
North Texas State College
Object Type:
Book
System:
The UNT Digital Library
Chemical Reactions In Crossed Molecular Beams
Even in its present primitive stage the molecular beam method promises to open up many opportunities for detailed studies of reactive collisions. The early results described here have revealed several features inaccessible to the traditional methods of kinetics. We hope this program of beam studies will ultimately provide the basis for constructing a theory of the molecular mechanics of reactions. By borrowing what are now everyday techniques in nuclear physics (modulation of the beams; mass analysis and counting of detected ions) it appears possible to gain from four to six orders of magnitude.
Date:
July 1961
Creator:
Herschbach, Dudley R.
Object Type:
Report
System:
The UNT Digital Library
THE CORROSION OF ALUMINUM ALLOYS IN THE OAK RIDGE RESEARCH REACTOR
A corrosion testing program designed to estimate the potential service life of aluminum alloys used in the construction of the Oak Ridge Research Reactor (ORR) cooling systems has been in progress for over two years. The five alloys (1100, 3003, 5052, 5154, and 6061) used to the greatest extent in the reactor exhibited continuously decreasing corrosion rates since the first 500-hr inspection. Samples exposed in the core-cooling loop have shown a decrease in corrosion rate from a 2.6 mpy maximum for one group during the first 500 hr to an over-all average of less than 0.1 mpy for another group after a full year in test, with the maximum metal loss less than 0.1 mils. Results indicate that with suitable water treatment the aluminum alloys used in the ORR may be expected to give satisfactory performance for many years. Based on the generalized corrosion rates alone, 40 to 50 years of service life may be expected. However, since occasional localized corrosion has been observed (rarely), minor repairs will almost certainly be required before that time. (auth)
Date:
July 1, 1961
Creator:
Neumann, P.D.
Object Type:
Report
System:
The UNT Digital Library
Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam
The alloying of zirconium to improve corrosion resistance has an empirical basis, and satisfactory explanations for the alloying effects are not available. A theory of compensating valencies in the corrosion oxide is proposed, in which cations of lower and higher valence than zirconium (+4) are present in ratios such that electrostatic neutrality is ensured. An example is an alloy containing equimolar amounts of scandium (+3) and niobium (+5). A number of zirconium alloys were prepared in which scandium or yttrium were paired with elements capable of a +5 or +6 valence. The ternary alloys containing scanadium were superior to the alloys combining yttrium. The alloys containing scandium plus molybdenum, tantalum, or tungsten had relatively long lifetimes in steam at 540 deg C and 600 psi as compared with other alloy combinations, including Zircaloy-2. A quenched alloy containing 0.025 wt% Sc and 0.053 at.% Mlo, that is, 0.05 mol.% of each additive, corroded approximately according to a cubic law up to 758 hr, at which potnt the rate suddenly increased in a manner suggesting hydrogen damage. Examination of the oxide film from alloys containing scandium and molybdenum showed only monoclinic ZrO/sub 2/. It is believed that stabilization of this form of …
Date:
July 1, 1961
Creator:
Misch, R.D. & Van Drunen, C.
Object Type:
Report
System:
The UNT Digital Library
Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam
Report concerning the corrosion of several ternary zirconium alloys using distilled water at 350 degrees Celsius or ssteam heated to 540 degrees Celsius and 600 psi.
Date:
July 1961
Creator:
Misch, R. D. & Van Drunen, C.
Object Type:
Report
System:
The UNT Digital Library
The Cross Section, Volume 8, Number 2, July 1961
Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.
Date:
July 1961
Creator:
High Plains Underground Water Conservation District No. 1 (Tex.)
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
CURRENT STATUS OF THE AC IONIZATION CHAMBER
ABS>The design concept of an a-c ionization chamber and its supporting electronics is described. Several designs are possible and the sensors can be tailored to specific requirements when necessary. Mode of operation, signal voltage development, and switching frequency are discussed. High-sensitivity operation is described. Requirements for high-temperature, power-level operation are outlined. (M.C.G.)
Date:
July 1, 1961
Creator:
Rusch, G.K.
Object Type:
Report
System:
The UNT Digital Library
Damage to Site 26 Wildhorse Creek
Photograph of Washita watershed, damage to front slope of Site 26 Wildhorse Creek Watershed. Dam runs almost due east and west. Part of slope was rip-rapped with rock from spillway but rock lacked about 6 feet being high enough to prevent this damage. SCS plans to repair this damage.
Date:
July 1, 1961
Creator:
Brown, Bob R.
Object Type:
Photograph
System:
The Gateway to Oklahoma History
Damage to Site 26 Wildhorse Creek
Photograph of Washita watershed, damage to front slope of Site 26 Wildhorse Creek Watershed. Dam runs almost due east and west. Part of slope was rip-rapped with rock from spillway but rock lacked about 6 feet being high enough to prevent this damage. SCS plans to repair this damage.
Date:
July 1, 1961
Creator:
Brown, Bob R.
Object Type:
Photograph
System:
The Gateway to Oklahoma History
A DESCRIPTION OF INTEGRAL PHYSICS DATA FOR FAST REACTOR DESIGN
Integral physics data for fast reactor design are discussed. The measurements needed include those of critical mass, shape factor, detector ratios, neutron spectra, material replacement experiments, reflector savings, neutron lifetime, Rossi- alpha , and similar quantities. Topics covered include Pu- and U/sup 233/-fueled systems, highly enriched U/sup 235/ systems in optimum geometry, uranium cores of various enrichments and dilutions, extreme geometry critical experiments, specific reactor systems, core mockup inhomogeneities, spectral studies and detector ratios, uranium equilibrium spectrum data, materialreplacement measurements, fast reactor dynamics, and suggested future experiments and experimental programs. (M.C.G.)
Date:
July 1, 1961
Creator:
Loewenstein, W.B. & Meneghetti, D.
Object Type:
Report
System:
The UNT Digital Library
Design Criteria for Steel in Nuclear Reactors
S>Criteria for stress analysis and structural design with steel for the critical components of nuclear plants are presented. An effort was made to integrate the effects on the strength of steel of the coexisting phenomena, such as mechanical and thermal loads, stress cycling and fatigue, creep and creep rupture, irradiation, and loss of ductility. Extensive use of the plastic region of steel was made for the accommodation of thermal stresses. The concept of cumulative damage in the plastic region was expounded for thermal fatigue and creep. A short description is given of the five avenues followed for the development of a theory governing the strength of materials. An approach was taken up that attempts to establish a "theory of fatigue" based on experiments. (auth)
Date:
July 1, 1961
Creator:
Fistedis, S.H.
Object Type:
Report
System:
The UNT Digital Library
Design Study of Portable Thermoelectric Nuclear Systems
Design studies were performed and costs were estimated for an air transportable, 10 Mw(t), pressurized light water thermal circulation reactor, combined with a direct conversion thermoelectric generator and static electrical inversion equipment. This TCR-TE'' concept appears to have potential for ultimate use as a remote unmanned power station. Based on an extrapolation of present reactor technology and on assumed thermoelectric materials properties forecasted to January 1, 1963, a net a-c electrical output of 315 Kw is estimated, assuming the use of 80 deg F local water for cooling purposes. An alternate concept using 80 deg F air for cooling produces 271 Kw, net. These electrical output figures can be improved significantly through a recommended research and development effort. The design and construction of a prototype plant is also recommended. (auth)
Date:
July 1, 1961
Creator:
Chajson, L.; DelCampo, A. R. & Kellogg, H.B. et al
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF A PROCESS FOR SODIUM BONDING OF EBR-II FUEL AND BLANKET ELEMENTS
Procedures for assembling EBR-II fuel elements with annular sodium bonds between the uranium rods and the stainless steel claddings are outlined. The results of several meltdown and uranium-settling experiments are given. Bonding experiments were performed: furnace bonding, submerged canning, ultrasonic bonding, centrifuging, pressure pulsing, and vibratory bonding. Vibratory bonding was chosen for the production of the first EBR-II core. (D.L.C.)
Date:
July 1, 1961
Creator:
Sowa, E.S. & Kimont, E.L.
Object Type:
Report
System:
The UNT Digital Library
Doings in Denton (Denton, Tex.), July 1961
Monthly newsletter from Denton, Texas that includes news and information about former and current residents and community happenings along with advertising.
Date:
July 1961
Creator:
Headlee, E. J.
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Electrical Properties of Glass. A Bibliography
A bibliography on the electrical properties of glass is presented. The 267 references covering the period from 1930 through 1960 are arranged according to subject. An author index is included. (M.C.G.)
Date:
July 1, 1961
Creator:
Kepple, R.
Object Type:
Report
System:
The UNT Digital Library
THE EXPERIMENTAL BERYLLIUM OXIDE REACTOR. MARITIME GAS-COOLED REACTOR PROGRAM
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 use either in a merchant ship propulsion system or an intermediate size central station power plant in the 20 to 100 Mw(e) size range. The EBOR is a l0 Mw(t) test of the basic fuel element and moderator designs. It is capable of being up-graded in power at a later date to a test of the nuclear reactor turbine concept. The objective of the experiment is outlined. The principal reactor components to be tested and the test facility are described. (auth)
Date:
July 1, 1961
Creator:
Moore, W.C.
Object Type:
Report
System:
The UNT Digital Library
Extrusion of Uranium Tubes
Technical report. From Abstract : "Several hundred long, thin-walled uranium tubes were extruded to close dimensional tolerance by a potentially low cost fabrication process in commercial facilities. The principal process steps were; forging uranium ingots, machining the forged ingots into billets, and extruding the billets into tubes. Some 750 tubes (maximum dimensions: 3.5 inches in diameter and 15 feet long) were fabricated by this process. Dimensional control was excellent in that 88% of the tubes were within +/- 0.010 inch of average dimensions over their entire length."
Date:
July 1961
Creator:
Fisher, R. E.
Object Type:
Report
System:
The UNT Digital Library
Fabrication of Fuel Rods by Tandem Rolling
From introduction: "The purpose of this report is to present the details of the exploratory and developmental work on tandem rolling, and the subsequent fabrication of tandem rolled fuel rods for irradiation testing in the Vallecitos Boiling Water Reactor."
Date:
July 1961
Creator:
Lingafelter, J. W.
Object Type:
Report
System:
The UNT Digital Library