Resource Type

Texas S-R Suspensions by County: 1959 (open access)

Texas S-R Suspensions by County: 1959

Annual report providing tabular statistical information about license safety responsibility (S-R) suspensions of drivers in Texas for failure to file or show proof of financial responsibility resulting from convictions and accidents, broken down by county and by locations of out-of-state accidents. It also includes very basic overview information about filing proof of financial responsibility.
Date: January 6, 1960
Creator: Texas. Department of Public Safety. Statistical Services.
Object Type: Report
System: The Portal to Texas History
Solution of the Monoenergetic Boltzmann Equation in an Infinite Homogeneous Nonmultiplying Medium with Linearly Anisotropic Scattering and Isotropic Plane Source (open access)

Solution of the Monoenergetic Boltzmann Equation in an Infinite Homogeneous Nonmultiplying Medium with Linearly Anisotropic Scattering and Isotropic Plane Source

The solution of the monoenergetic Boltzmann equation in an infinite homogeneous, nonmultiplying medium with linearly anisotropic scattering and an isotropic plane source is given and compared with the corresponding solution for isotropic scattering. The effective source strength for the asymptotic flux turns out to be the same as that for isotropic scattering to first order in Σa/Σ.
Date: September 6, 1960
Creator: Inonu, Erdal
Object Type: Report
System: The UNT Digital Library
A Model of the PRTR Mark I Fuel Element for Heat Transfer Experiments (open access)

A Model of the PRTR Mark I Fuel Element for Heat Transfer Experiments

The purpose of this document is to describe the design and construction of a full-scale, electrically-heated model of a 19-rod PRTR fuel element for use in heat transfer experiments.
Date: July 6, 1960
Creator: Hammond, J. E.
Object Type: Report
System: The UNT Digital Library
Fluidized-Bed Calcination Studies with Stimulated ICPP Waste Solution (open access)

Fluidized-Bed Calcination Studies with Stimulated ICPP Waste Solution

At the present time, high-radioactivity-level wastes at Hanford are neutralized and stored as liquid in underground tanks lined with mild steel. This method of storage is relatively inexpensive and is satisfactory on a short-term basis. However, on a long term basis, liquid storage is less desirable than solid storage because of the greater mobility of the liquid. In addition, storage as aa solid would significantly reduce the volume of waste stored. Consequently, various research and development studies have been undertaken in an attempt to develop a practical waste solidification.
Date: June 6, 1960
Creator: Schneider, K. J.
Object Type: Report
System: The UNT Digital Library
Aluminum Alloy Work at Hanford (open access)

Aluminum Alloy Work at Hanford

Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
Date: May 6, 1960
Creator: Bowen, H. C.
Object Type: Report
System: The UNT Digital Library
Twin Argon Welding of Alsi-Bonded Aluminum Clad Uranium Metal Fuel Elements (open access)

Twin Argon Welding of Alsi-Bonded Aluminum Clad Uranium Metal Fuel Elements

In the continuing search for better methods of effecting the secondary fusion welded closure in Alsi bonded aluminum clad uranium metal fuel element, an article on "The Twin-Argon Welding Process" by J. A. Donellon was recently found in the September 1954 issue if the British Welding Journal. From a review of the article, the process appeared to have enough possibilities to warrant exploring it. Communication were established with the General Electric Company, Ltd..
Date: May 6, 1960
Creator: Correy, Thomas B.
Object Type: Report
System: The UNT Digital Library
Classification of PuO2 Particles (open access)

Classification of PuO2 Particles

The Biology Operation, Hanford Laboratories, required plutonium dioxide particles in five different micron and sub-micron size ranges. These were to be supplied as a water suspension in small containers. It was necessary to design equipment, suitable for hood operation, which would give a satisfactory separation of these particles.
Date: January 6, 1960
Creator: Burnham, J. B.
Object Type: Report
System: The UNT Digital Library
Notes on Lattice Parameter Calculations (open access)

Notes on Lattice Parameter Calculations

In the last two or three years there has been a notable improvement in the knowledge and understanding of reactor lattice physics. During this interval, measurements of parameters have been improved and the methods of analysis have been greatly strengthened. It has become apparent that the classical ways for computing the lattice parameters are not sufficient. It is the purpose of this report to publish under one cover as much of the most recent information as possible.
Date: October 6, 1960
Creator: Joanou, G. D.
Object Type: Report
System: The UNT Digital Library
Genetic Influences On Mating Behavior In Drosophila Melanogaster (open access)

Genetic Influences On Mating Behavior In Drosophila Melanogaster

Certain aspects of mating behavior in two different types of Drosophila melanogaster females (Basc and Bv) and wildtype males (Samarkand) have been investigated and compared.
Date: December 6, 1960
Creator: Hildreth, Philip E. & Becker, Gweneth Carson
Object Type: Report
System: The UNT Digital Library
Possible Manifestations Of A Pion-Pion Interaction (open access)

Possible Manifestations Of A Pion-Pion Interaction

The pion-pion interaction is of great theoretical importance and must be understood before the other and more familiar interactions can be systematically analyzed. Therefore, various experiments to verify the existence of a P resonance in the w w system are proposed.
Date: January 6, 1960
Creator: Chew, Geoffrey F.
Object Type: Report
System: The UNT Digital Library
Avalanche Transistor Switching (open access)

Avalanche Transistor Switching

Introduction. High voltage silicon mass transistors have the ability to perform circuit functions similar to the gas thyratron tube. Upon being triggered the transistor junction breaks down, or "avalanches", and can conduct a large current for a short time. The rise time of the avalanche breakdown pulse can be short, and the delay between triggering and avalanching can be short and very consistent. This avalanche action is non-destructive if the amount of peak and average power being dissipated at the junction is limited by the circuitry.
Date: May 6, 1960
Creator: Rufer, Richard P.
Object Type: Report
System: The UNT Digital Library
A Plasma Cyclotron (open access)

A Plasma Cyclotron

In a previous report the adaptation of Stix's ion-cyclotron-wave-heating scheme to the mirror geometry was suggested. An experiment along these lines has been conducted for the past year by E. Chambers, using a tubular P.I.G discharge to provide the basic plasma. The Chambers experiment has been eminently successful in demonstrating the transfer of rf power along the P.I.G. (as along a co-axial conductor), and the resultant acceleration of ions. The power transfer is evident from the predominantly resistive rf impedance of the P.I.G. (1 - 10 ohms), the production of intense luminosity outside the dc P.I.G channel when the rf is turned on, and by the observation large signals with magnetic pick-up loops. The ion heating is demonstrated by direct measurement of ion current on a probe some centimeters outside the P.I.G., and by the observation of energetic charge-exchange neutrals. At the same time, the characteristic features of heating by ion-cyclotron-waves, as described by Stix, are only partly in evidence. The visible broadening of the P.I.G. channel and such fast-ion phenomena as neutral emission do seem to be maximal near the expected cyclotron resonance point. However, the rf impedance is anomalous both in magnitude and parameter dependence, and there are …
Date: April 6, 1960
Creator: Furth, Harold P.
Object Type: Report
System: The UNT Digital Library
Non-military Uses of Nuclear Explosions (open access)

Non-military Uses of Nuclear Explosions

Introduction. With the development of fission and subsequently of thermonuclear explosives, a very large source of cheap energy has become available. The problem of using this energy for peaceful purposes safely and economically presents itself as one of the most interesting and important of our time. In explosions the energy is released very suddenly. Conversion of this sudden release of energy at extremely high temperature and pressure into the form of useful work, either mechanical or chemical or thermal, must be accomplished in order for such explosions to have nonmilitary uses. The technical feasibility of such conversions in a number of different instances will be described in this article. At the same time one must be able to control nuisance effects. Examples of these are seismic effects, the blast and heat which at least in the atmosphere always accompany such explosions, and the problem of radioactivity. Even given the technical feasibility of these accomplishments, which in some cases seems quite clear from what is known already, one must prove economic feasibility. That is to say, one must show that the cost of certain nonmilitary undertakings will be considerably less by the use of nuclear explosions than by conventional methods.
Date: January 6, 1960
Creator: Brown, Harold
Object Type: Report
System: The UNT Digital Library
Preliminary petrographic study of rock from Nevada Test Site - Basalt Mesa (open access)

Preliminary petrographic study of rock from Nevada Test Site - Basalt Mesa

Discussing photographs of rocks from Basalt Mesa
Date: May 6, 1960
Creator: Anderson, E. E.
Object Type: Report
System: The UNT Digital Library
Process optimization 709 program (open access)

Process optimization 709 program

In the past two years a number of process optimization studies have been made with the aid of IBM machine programs. These programs have been designed to calculate optimum power levels and optimum goal exposures so that better insight could be gained for use in resolving plant operating plans. We feel that this approach has been highly successful. In January of 1960, a new program was written for the IBM 709 to incorporate the desirable features of the previous programs and to provide additional output data. This document is a description of the new programs.
Date: April 6, 1960
Creator: Turner, R. L. & Poor, C. F.
Object Type: Report
System: The UNT Digital Library
Variable goal exposure plans for production type fuel elements (open access)

Variable goal exposure plans for production type fuel elements

The purpose of this memorandum is to transmit revisions to the goal exposure plans of reference (1). The plans, herein, supersede the previous recommendations. Similar to the plans of reference (1), the exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle, as described and defined in references (2) and (3). When metal throughput is limited by ex-reactor physical capabilities to a level lower than the unrestrained requirements, exposures higher than those recommended in this document would be indicated, as explained in reference (4). In essence then, these plans represent minimum economical exposures for current production fuel types, on the basis of attempting to maximize plant returns. The adjustments recommended herein, stem solely from revised estimates of the metal performance level indices (C{sub R} values) of the various metal types.
Date: July 6, 1960
Creator: Bloomstrand, R. R.
Object Type: Report
System: The UNT Digital Library
Revisions to variable goal exposure plans for production type fuel elements (open access)

Revisions to variable goal exposure plans for production type fuel elements

The exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle. When metal throughput in limited by ex-reactor physical capabilities to a level lower than the unrestrained requirements, exposures higher than those recommended in this document would be indicated. In essence then, these plans represent minimum economical exposures for current production fuel types, on the basis of attempting to maximize plant returns. The adjustments recommended herein, stem solely from revised estimates of the metal performance level indicies (C{sub R} values) of the various metal types.
Date: December 6, 1960
Creator: Bloomstrand, R. R.
Object Type: Report
System: The UNT Digital Library
Program for Crud and Corrosion Studies for Proposed Hanford Reactor Conditions (open access)

Program for Crud and Corrosion Studies for Proposed Hanford Reactor Conditions

This report presents a proposed test program to study the corrosion of aluminum-clad fuel elements under conditions expected at the more severe conditions which will be encountered in operating the present Hanford reactor at higher power levels.
Date: September 6, 1960
Creator: Richman, R. B. & Dickinson, D. R.
Object Type: Report
System: The UNT Digital Library
PT-IP-297-A-FP, The effect of autoclave film damage on the incidence of groove pitting on X-8001 alloy fuel jackets (open access)

PT-IP-297-A-FP, The effect of autoclave film damage on the incidence of groove pitting on X-8001 alloy fuel jackets

The objective of this test is to evaluate the hypothesis that autoclave film damage is a necessary condition for groove pitting of X-8001 alloy fuel cladding.
Date: April 6, 1960
Creator: Hall, R. E.
Object Type: Report
System: The UNT Digital Library
C pile mark 1 overbore fuel element design (open access)

C pile mark 1 overbore fuel element design

It is necessary to provide the option of using either aluminum or zirconium tubes in the C pile 20-tube overbore test. A bumper-type fuel element has been designed to fit a fixed ribbed aluminum tube size; zirconium tube dimensions were then determined which will provide the same flow and pressure drop when the fuel element is changed from bumper type or self-supported without changing other fuel dimensions.
Date: October 6, 1960
Creator: Cahoon, R. D. & Nechodom, W. S.
Object Type: Report
System: The UNT Digital Library
Rear-face Parker fitting reaming (open access)

Rear-face Parker fitting reaming

Although a fuel reactor job procedure has not yet been prepared, techniques and equipment used in a current production test are adequate with minor modifications for full reactor Parker fitting reaming. With existing reactor hardware, available flow increases at B, D, and F Reactors would be limited to about 2,500 gpm. The extent of additional rear face piping problems which may be encountered as a result of reaming cannot in several instances be predicted with confidence at this time. It is expected that preliminary answers to currently foreseen problems will be available by April 1, 1961. To some extent, however, this is dependent on production tests under way or proposed, and will require coordination with various Manufacturing Operations. For vibration and flow problems in the downcomer approach piping, conclusive answers may not be available before July, 196l, although there is no positive evidence that the flow increases cannot be absorbed. Increased pressurization of effluent line junction boxes at 105-D has been solved by improved box venting. Increased flows resulting from reaming may require still greater venting capacity, which would be available for capital expenditures on the order of $3,000--$5,000 per area.
Date: December 6, 1960
Creator: Brinkman, L. B. & Corley, J. P.
Object Type: Report
System: The UNT Digital Library
Daily data sheets -- PT-IP-280 A: Ingot-alloyed dingot D-Reactor (open access)

Daily data sheets -- PT-IP-280 A: Ingot-alloyed dingot D-Reactor

The data consists of out and inlet temperatures, and panellit and header pressures, sorted according to date and tube-pile.
Date: April 6, 1960
Creator: Hall, R. E.
Object Type: Report
System: The UNT Digital Library
The glove box fire control studies: Interim report (open access)

The glove box fire control studies: Interim report

This report describes efforts to develop a safe, practical method to extinguish fires inside contaminated gloveboxes. Oil, trash, and metal fires were set to test various materials and techniques. Dry chemical extinguishers and MgO sand proved more practical than flooding the boxes with either CO/sub 2/ or argon. Gas replacement techniques pressurized the boxes and greatly increased the risk of outside contamination. 5 figs. (TEM)
Date: October 6, 1960
Creator: King, R.R. Jr.
Object Type: Report
System: The UNT Digital Library
Radiation Effects on Boron-Containing Compounds (open access)

Radiation Effects on Boron-Containing Compounds

Report discussing studies on changes within irradiated elemental boron, boron carbide, and zirconium diboride. Materials, methods, and experimental data are included.
Date: January 6, 1960
Creator: Hamman, Donald J. & Schall, Paul
Object Type: Report
System: The UNT Digital Library