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533
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205
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Ground-Water Resources of the Lower Rio Grande Valley Area, Texas: Volume 2. Records of Wells, Drillers' Logs, Water Levels in Wells, and Chemical Analyses of Water
"This publication is the second of a two volume report on the ground-water resources of the Lower Rio Grande Valley area in Texas...The Lower Rio Grande Valley area, as defined in this report, consists of Cameron, Hidalgo, Starr, and Willacy Counties; however, records of selected wells and drillers' logs in Kenedy County were used to supplement basic data" (Foreword).
Date:
February 1961
Creator:
Baker, Roger C. & Dale, O. C.
System:
The Portal to Texas History
Ground-Water Resources of the Lower Rio Grande Valley Area, Texas: Volume 1
"This publication constitutes the first of a two-volume report on the ground-water resources of the Lower Rio Grande Valley area which consists of Cameron, Hidalgo, Starr, and Willacy Counties in southern Texas" (Foreword).
Date:
February 1961
Creator:
Baker, Roger C. & Dale, O. C.
System:
The Portal to Texas History
Texas Driver License Suspensions: 1960
Annual report providing tabular statistical information about license suspensions and denials for drivers in Texas, broken down by county and by various other criteria.
Date:
1961
Creator:
Texas. Department of Public Safety. Statistical Services.
System:
The Portal to Texas History
Texas S-R Suspensions by County: 1960
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 4, 1961
Creator:
Texas. Department of Public Safety. Statistical Services.
System:
The Portal to Texas History
Fuel-Cycle Analysis and Proposed Fuel and Burnable Poison Distribution and Loading for the HFIR and HFCE-2
Further calculations have been made to determine the desired radial fuel distribution in the HFIR and in the forthcoming HFIR critical experiment. In the process the design of the core was changed to include a 1-cm-thick annular space of water between the two nearly equally thick fuel annuli, a metal-to-water ratio in the fuel annuli of 1.0 (0.050 in. thick plates and coolant channels ) was specified, and the active length of the core was increased from 18 to 20 in. Results of the calculations indicated that the largest ratio of maximum meat thickness to minimum meat thickness occurred in the inner fuel annulus and was equal to 3.6, while the maximum fuel concentration occurred in the outer fuel annulus and was equivalent to about 0.7 g of U-235/cm^3 of meat. The total U-235 loading for this core was 8.01 kg, which results in a core lifetime of about 14 days.
Date:
February 2, 1961
Creator:
Cheverton, R. D.
System:
The UNT Digital Library
Generalized Heat Conduction Code for the IBM-7090 Computer
The IBM-70% code GHT has been programmed for the 7090computer, to be run under control of the IBM-7090 FORTAN Monitor System. By eliminating the use of tapes for intermediate number storage, it has been possible to reduce computing time by a factor of 26 over the 704. A minimum of three tapes are required; one for input, one for output, and the System tape. One scratch tape is required for transient problems, and one punch tape is required if the steady-state temperature distribution is to be punched on cards.
Date:
February 9, 1961
Creator:
Fowler, T. B.
System:
The UNT Digital Library
Equilibrium Adsorption of Krypton and Xenon on Activated Carbon and Linde Molecular Sieves
Equilibrium krypton and xenon adsorption isotherms were obtained for four varieties of charcoal and for Linde Molecular Sieves Types 4A and 5A, generally at 0, 25, and 60°c. Such data are of interest in connection with design and evaluation of adsorbers for radioactive noble gas fission products. The isotherms were fitted, by linear regression analysis, to straight-line forms of the Freundlich and Langmuir equations. The Freundlich linear equation gave the better fit and the parameters of this equation are presented for each of the isotherms. Also presented are the constants for an equation representing the temperature dependence of arbitrary adsorption coefficients, the coefficients having been calculated from the Freundlich isotherm parameters. Some aspects of the applicability and accuracy of these results are discussed.
Date:
February 14, 1961
Creator:
Ackley, R. D. & Browning, W. E., Jr.
System:
The UNT Digital Library
On the Translation of Boolean Expressions
A program translates an algebraic language like Algol into the machine language of an electronic computer must perform the following functions.
Date:
February 9, 1961
Creator:
Grau, A. A. & Bottenbruch, H. H.
System:
The UNT Digital Library
Processing of Beryllium Oxide Fuels
Preliminary results from experiments on the dissolution of beryllium metal and sintered UO2-BeO fuel pellets are reported. In all cases the pellets were fired in hydrogen at 1650-1800°C. Uranium, from UO2-BeO pellets containing more than 60% UO2, is readily leached with boiling 6-13 M HNO3 in about 6 hr. The BeO in these pellets dissolves only slowly in nitric acid; however, in 8 M HNO3-0.2M NaF, it dissolves at about the same rate as the UO2. Sintered pellets containing less than 10% UO2 do not dissolve rapidly in common aqueous reagents. The highest rates are obtained in boiling acidic fluoride solutions; e.g., sintered BeO and BeO-8% UO2 are dissolved initially at a rate of about 1.7 mg min-1cm-2 (13 mils/hr) in boiling 5.8 M NH4HF2.
Date:
February 13, 1961
Creator:
Warren, K. S. & Perris, L. M.
System:
The UNT Digital Library
Chemical Development Section C Progress Report for December 1960 and January 1961
Test work was completed on development of a stripping method for the amine extraction (Amex) process which produces a concentrated uranyl nitrate solution for shipment to the refinery. This procedure offers potential cost savings by simplifying the overall mill-refinery flowsheet. The process involves treatment of the amine extract with calcium nitrate solution to convert the uranium in the solvent to a nitrate complex, stripping the uranium with water or dilute nitric acid, and recovery of nitrate from the solvent for recycle by contact with a lime slurry.
Date:
June 2, 1961
Creator:
Brown, K. B.
System:
The UNT Digital Library
Multi-temperature Cross Section Tape for the GNU Multigroup Calculation
A cross section tape has been prepared containing data for elements of most interest for aqueous homogeneous reactor multigroup diffusion calculations involving combinations of 150, 200, 240, 260, and 280°C temperatures. This tape permits multigroup analysis of a reactor in which two or more regions are at different temperatures.
Date:
January 25, 1961
Creator:
Vondy, D. R.
System:
The UNT Digital Library
Multiple Controllers for a Single Process
A multiple controller system for a single process is formulated in block diagram form. It is shown that for the general case of n controllers and one type of cross coupling, the system equations can be reduced to the standard forms of servomechanism theory. The effects of failure in individual controllers are examined, and it is demonstrated that the system shows considerable promise for both reliability and maintenance without process interruption.
Date:
January 25, 1961
Creator:
Weaver, C. H.
System:
The UNT Digital Library
THOROBRED - An IBM-704 Code for Steady State Nuclear and Economic Calculations of Two=Region Homogeneous Reactors
THOROBRED is an IBM-704 code for the calculation of nuclear and economic characteristics of two-region homogeneous reactors operating on a U-Th fuel cycle in the steady state. The major input variables are reactor dimensions, power level, thorium concentration, chemical and purification systems cycle times, corrosion rates, fraction of Pa loss, and nuclear and economic data. The output includes equilibrium isotope concentrations, neutron balance, and a breakdown of fuel cost. Running times are normally less than one minute per case.
Date:
January 17, 1961
Creator:
Jaye, S. & Fowler, T. B.
System:
The UNT Digital Library
Xenon and Samarium Poisoning
The equilibrium and maximum override values for xenon and samarium poisoning have been computed using the recently issued effective cross sections of C. H. Westcott. Values are given as a function of specific power, neutron temperature, and epithermal flux content.
Date:
January 23, 1961
Creator:
Carlsmith, R. S.
System:
The UNT Digital Library
A Useful Solution for Short Cylindrical Shells and Other Applications
The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notation is used throughout the derivations; however, a knowledge of matrix theory is not need for application of the results.
Date:
February 14, 1961
Creator:
Moore, S. E.
System:
The UNT Digital Library
Sources and Availability of Helium
A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date:
January 19, 1961
Creator:
Fraas, A. P.
System:
The UNT Digital Library
Some Heat Transfer Characteristics of ORR Fuel Elements
Analyses are generally made at the ORR with a view toward determining the surface temperatures of fuel plates.
Date:
January 19, 1961
Creator:
Wett, J. F., Jr.
System:
The UNT Digital Library
Revised Version of HFIR Critical Experiment-2 (HFCE-2)
A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date:
January 16, 1961
Creator:
Kasten, P. R. & Cheverton, R. D.
System:
The UNT Digital Library
Bremsstrahlung Absorption Measurements from Sr^90 TiO3
The absorption in lead of Bremsstrahlung X radiation from a Sr^90 TiO3 pellet in the proximity of Hastelloy "C" was measured. The tenth value layer of the more energetic components of the X-ray continuum was determined to be 1.60 inches.
Date:
January 13, 1961
Creator:
Butler, T. A. & Pierce, E. E.
System:
The UNT Digital Library
Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960
A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date:
January 11, 1961
Creator:
Sadowski, G. S.
System:
The UNT Digital Library
Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop
Simulated reactor fuel solutions were circulated at temperatures as high as 365°C in a small titanium pump loop. A hydroclone separator separated heavy phases formed at high temperatures. As the temperature of the solution was increased beyond the two-liquid-phase temperature (327°C), the salt concentration of the light phase decreased and the acid concentration increased. The mole ratios of uranium to sulfate, uranium to copper, and uranium to nickel in the light phase decreased in the same proportion in the temperature range of 330 to 365°C. Corrosion of titanium and Zircaloy-2 specimens was insignificant during the relatively short exposure periods.
Date:
January 6, 1961
Creator:
Griess, J. C.; Baker, J. M. & Savage, H. C.
System:
The UNT Digital Library
ORR Startup Accident and Cooling Flow Coastdown Analog Analysis
Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is increased to the point where the level scram must be set above 50 Mw).
Date:
January 4, 1961
Creator:
Stone, R. S. & Colomb, A. L.
System:
The UNT Digital Library
Fission Product Release from UO2 and by High Temperature Diffusion and Melting in Helium and Air.
The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release. Two of the most important variables not investigated in the present report are the influence of metal cladding and the difference in internal nuclear heating as opposed to external radiant heating. In addition a significant uncertainty exists in the understanding of diffusion through large masses such as might result from a scaled-up melt down in a reactor.
Date:
February 8, 1961
Creator:
Parker, G. W.; Creek, G. E. & Martin, W. J.
System:
The UNT Digital Library
Design Study of a Pebble-Bed Reactor Power Plant
Sanderson & Porter have carried out a series of studies over the last four years which indicate that the pebble-bed reactor way be an attractive way to obtain low-cost power. At the request of the Atomic Energy Commission, two design studies have been carried out on this concept at the Oak Ridge National Laboratory. The first of these a preliminary design of a 10-Mw(t) reactor experiment, the PRRE, was initiated September 10, and a report on the study was issued November 1960. The second phase of the work, a conceptual design study of a 330-Mw (e) central station, was initiated November 1, and is the subject of this report.
Date:
May 11, 1961
Creator:
Fraas, A. P.; Carlsmith, R. S.; Corum, J. M. & Foster, J.
System:
The UNT Digital Library