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Office of Scientific & Technical Information Technical Reports
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654
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443
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367
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304
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208
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2010 Census P.L. 94-171 County Block Map
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Car Coupler.
Patent for car coupler heads. This object has coupler heads that, when set in position, automatically lock.
Date:
September 11, 1923
Creator:
Tucker, Roger V.
Object Type:
Patent
System:
The Portal to Texas History
Lee College Courier, Volume 4, Number 18, September 1995
Newsletter of Lee College discussing news, events, and other updates.
Date:
September 11, 1995
Creator:
Lee College (Baytown, Tex.)
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Balanced Dairying: Economics, Volume 18, Number 2, September 1998
Newsletter of the Texas Agricultural Extension Service discussing topics related to economic aspects of raising dairy cows, dairy production, and managing dairy operations.
Date:
September 11, 1998
Creator:
Texas Agricultural Extension Service
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Pecan Pest Management Newsletter, Volume 94, Number 6, July 1994
Newsletter focusing on pecan disease and pest control in Texas, including prevention, identification, treatment, and educational opportunities.
Date:
July 11, 1994
Creator:
Texas Agricultural Extension Service
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Register, Volume 48, Number 32, Pages 4329-4440, August 11, 2023
A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.
Date:
August 11, 2023
Creator:
Texas. Secretary of State.
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Parks & Wildlife News, June 11, 1980
Weekly newsletter discussing natural resources, parks, hunting and fishing, and other information related to the outdoors in Texas.
Date:
June 11, 1980
Creator:
Texas. Parks and Wildlife Department.
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Behavior of Transistors in a Magnetic Field
Experiments are described which show that magnetic fields can exert a controlling influence on the operating characteristics of point contact transistors. The effect is especially evident when the transistor is operated in its negative resistance region. The frequency of an oscillator can be varied, or a switch made to trigger by applying a magnetic field to the transistor. Some applications of the principle are suggested; many more are evident.
Date:
August 11, 1954
Creator:
Sander, Howard H.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Local Reactivity "Worth" in the HRT
The effect of adding small quantities of fuel or poison to the HRT has been estimated using perturbation theory. The results have been reduced to a single relation and a set of graphs which make the estimation of added reactivity relatively simple. The perturbation theory results are compared with multigroup results and reasonable agreement is demonstrated; however, there is some question concerning the prompt neutron lifetime.
Date:
October 11, 1960
Creator:
Jaye, S. & Vondy, D. R.
Object Type:
Report
System:
The UNT Digital Library
Dry Maintenance Facility for the HRT
A portable shield has been designed, developed, fabricated and shop tested to provide the HRT with a facility for direct dry maintenance operations. It provides temporary replacement for any one of the lower roof plugs and should permit many operations to be performed without flooding the reactor cell with water.
Date:
October 11, 1960
Creator:
Holz, P. P.
Object Type:
Report
System:
The UNT Digital Library
Two-Liquid-Phase Temperature Limits for the Homogeneous Reactor Fuel Solution and its Concentrates; Comments on Solid-Liquid Equilibria.
Temperatures are given at which two liquid phases form in a synthetic homogeneous reactor fuel solution and its concentrates. The data show a two-liquid-phase boundary temperature of 332°C for the Particular HRT Fuel composition and a flat minimum temperature of 305°C for the initial solution concentrated between 300 and 329°C are presented to indicate solution stability in this temperature region. Some related comments on current HRT operations are given.
Date:
August 11, 1959
Creator:
Marshall, W. L.; Gill, J. S. & Moore, R. E.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Temperature and Composition on the Mercury Vapor Pressure in the Uranium-Mercury System
The use of mercury as a solvent in the recovery of uranium from spent fuels is of the interest at Oak Ridge National Laboratory. The vapor pressure of mercury is lowered by increased concentration of uranium. By dew-point measurements, the vapor pressure at 175°C was found to very between 2 and 8mm of mercury, and at 375°C, between 300 and 1100 mm of mercury, depending upon composition as described below. Plots of the log of mercury vapor pressure vs. the reciprocal of absolute temperature gave a family of straight lines. Each line corresponded to one of the composition: UHg2, UHg3, UHg4, and a saturated solution of UHg4 in Hg. No Mutual solubility of the intermetallics was indicated.
Date:
June 11, 1959
Creator:
Forsberg, H. C.
Object Type:
Report
System:
The UNT Digital Library
Removal of Fission Product Gases from reactor Off-Gas Streams by Adsorption (Presented at American Nuclear Society Meeting, Detroit, Michigan, December 10, 1958)
In the operation of nuclear reactors, nuclear fuel reprocessing plants and in-pile experiments, special provision must be made for disposal of gaseous fission products to prevents contamination of the atmosphere to an unacceptable degree. A disposal process is described in which the noble gas fission products, krypton and xenon, are delayed relative to the sweep gas by physical adsorption as they pass through an adsorbent such as activated charcoal. A theoretical plate analysis, and has been verified experimentally. The retention time for a gas present in trace concentration is proportional to the amount of charcoal in the adsorber bed and to the adsorption coefficient which is evaluated experimentally for a particular combination of materials and conditions. The retention time is inversely proportional to the volume flow rate if the sweep gas.
Date:
June 11, 1959
Creator:
Browning, W. E.; Adams, R. E. & Ackley, R. D.
Object Type:
Report
System:
The UNT Digital Library
A Comparison of Elementary Criticality Calculations with Experimental Results
Several experiments have been performed at ORNL with light water solutions of uranyl nitrate (highly enriched in either U^233 or U^235) in an essentially bare sphere 27 inches in diameter. This report presents the results of several calculations with elementary bare reactor theory and a discussion of the observed discrepancies between the calculated and experimental results. If the observed critical concentration is used in the calculations, the calculated effective multiplication constant is less than unity' thus a higher critical concentration would be predicted than is actually observed.
Date:
June 11, 1959
Creator:
Nestor, C. W., Jr
Object Type:
Report
System:
The UNT Digital Library
Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-1 and E-2
After two batches (~ 340 kg) of fluoride salt from the ARE were reprocessed, pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF6) escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF6 product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The product met both chemical purity and activity specifications for product level UF6. Decontamination from fission products was essentially complete. A gross gamma D.F. was apparently limited by the low activity of the feed salt.
Date:
May 11, 1959
Creator:
Culler, F. L.
Object Type:
Report
System:
The UNT Digital Library
High-Frequency Titration as Applied to the Determination of Thorium, Uranium, Sulfate, and Free Acid. Parts I Through V.
The technique of high-frequency titrimetry has been applied to the determination of thorium, uranium, sulfate, and free acid. In Part I of this report, the reproducibility of the method for the titration of standard solutions which contained 50mg of thorium in the absence of interferences is established. The coefficient of variation of the method, under these conditions, was found to be less than one per cent. In Part II, the effect of uranium on the high-frequency titration of thorium, as well as the application of the method to actual samples, is discussed. Uranium in a ratio of 5 to 1 to thorium can be tolerated. When the method is applied to the analysis of representative samples, the coefficient of variation is one per cent.
Date:
May 11, 1959
Creator:
Menis, Oscar
Object Type:
Report
System:
The UNT Digital Library
Recrystallized Texture of Alpha Uranium
Uranium was plastically deformed 90% at room temperature by unidirectional rolling to a foil 0.002-inches thick. Specimens were recrystallized in the alpha region and several pole figures obtained from 0 to 40 degrees. From these, the preferred orientation was found to be in a spread of idealized (11) [010] about [010].
Date:
January 11, 1955
Creator:
Seymour, W. & Duffey, J.
Object Type:
Report
System:
The UNT Digital Library
Gas Plated Coatings on Metals and Alloys : Progress Report No. 1
The object of this project is to conduct studies on the coating of metals and alloys by the gas plating process. Coatings to be studied consist of chromium on copper; alloys of nickel chromium on copper; molybdenum on stainless steel and Inconel; chromium on stainless steel and Inconel; and tungsten and molybdenum and their carbides on stainless steel and Inconel.
Date:
March 11, 1953
Creator:
Nack, Herman & Whitacre, John R.
Object Type:
Report
System:
The UNT Digital Library
Grüneisen's Law and the Fusion Curve at High Pressure
A method to determine the correction to Grüneisen's law corresponding to the effect of the electrons at high pressure. It is assumed that the lattice contribution to the pressure is small and that the equation of state of the solid can be approximated by results of the statistical Thomas-Fermi atom model for the electron pressure.
Date:
April 11, 1955
Creator:
Gilvarry, J. J. (John James), 1917-
Object Type:
Report
System:
The UNT Digital Library
A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia
The continuous dissolution of 304 stainless steel and stainless steel-UO2 alloy in dilute aqua regia was studied with subsequent stripping of the dissolver product to remove chloride ion. The process has the advantage of producing, by means of a simple head end treatment, a solvent extract feed in a conventional nitric acid medium so that existing solvent extraction processes, materials of construction and waste disposal methods can be used. The purposes of this study were to investigate the variables affecting the dissolution process and to obtain dissolver scale-up data, and to investigate the removal of chloride from the dissolver product and the variables affecting the stripping operation. A continuous flooded pot dissolver was used. It has the advantages of stability of operation and ease of control in comparison with column dissolvers and requires a minimum of mechanical processing prior to dissolution. Stripping of the dissolver product to remove chloride ion was studied in a 4-in. diameter Pyrex bubble-cap column containing 12 single bubble cap plates. Continuous dissolution rates and dissolver product stainless steel loading were correlated with aqua regia feed composition, acid feed rate and surface area exposed to reaction. Profiles of chloride concentration down the stripping column were obtained …
Date:
October 11, 1957
Creator:
Kitts, F. G. & Perona, J. J.
Object Type:
Report
System:
The UNT Digital Library
Experiments on the Release of Fission Products from Molten Reactor Fuels
Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types, have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of rare gases, iodine, bromine, cesium, and rubidium. In the presence of air or water vapor, strontium and other fission products are not released. At trace concentration of fission products, slow melting of the APPR plate at 1525 C in air or steam effected the release of 50% of the rare gases, 33% of the iodine, 9% of the cesium, and traces of strontium. After 25% burn-up, the cesium value increased to about 60%. Aluminum alloy of the MTR type, also at trace concentration, upon melting at 700 C released up to 2% of the iodine, 10% of the rare gases, and negligible portions of other fission products. Zirconium alloy of the STR type after 15% burn-up, when melted at 1850 C, released up to 95% of the rare gases, 90% of …
Date:
March 11, 1958
Creator:
Parker, George W. & Creek, George E.
Object Type:
Report
System:
The UNT Digital Library
The Reaction of Zirconium with Uranium Dioxide
An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date:
June 11, 1957
Creator:
Robinson, M. T.
Object Type:
Report
System:
The UNT Digital Library
Cross Sections for OCUSOL-A Program
The OCUSOL-A program (ORNL-CF-57-6-4) for Univac is a modification of the Eyewash (ORNL-1925) multi-group, multi-region reactor code. The group=energy-lethargy-temperature relationship are given in Table A. The element code numbers are given in Table B. The cross sections now on the sigma-tape are given in tables in the Appendix numbered with the element code number. This technical report explains the bases for choosing the cross sections.
Date:
June 11, 1957
Creator:
Roberts, J. T. & Alexander, L. G.
Object Type:
Report
System:
The UNT Digital Library