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Congressional Research Service Reports
512
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213
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96
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85
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34
John F. Kennedy, Dallas Police Department Collection
34
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28
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18
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2
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2
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20
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18
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17
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16
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Zircex Uranium Sublimate Loss
"One of the limitations of the Zircex Process is the large percentage loss of U which is carried off with the volatile ZrCl/sub 4/. Since the ratio of U to Zr in the fuel element is quite small (< 1%), a large percentage of U loss can be caused by small amounts of U in the ZrCl/sub 4/ sublimate. The U loss must be kept below 1% if the Zircex Process is to be adapted to industrial scale processing."
Date:
January 24, 1958
Creator:
Jaworowski, T. R. & King, III, C. J.
System:
The UNT Digital Library
RAYPAC : a Special-Purpose Analog Computer
As an aid in forecasting possible blast damage in areas distant from a bomb burst point, a special-purpose electronic analog computer has been developed. Sound ray paths (orthogonal trajectories to sound wave front) are computed as a function of meteorological conditions.
Date:
March 24, 1955
Creator:
Durham, H. B.
System:
The UNT Digital Library
The Equation of State of Water on the Thomas-Fermi Model
Two methods are described for extending the Thomas-Fermi model of a compressed atom to molecules or mixtures of the type Z Zn. The methods are applied to H2O at zero temperature to determine pressure and internal energy as functions of the density, the position of the protons relative to the oxygen nucleus, and the electrostatic potential distribution within the molecule.
Date:
October 24, 1955
Creator:
Latter, A. & Latter, R.
System:
The UNT Digital Library
Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders. Appendices
The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date:
May 24, 1961
Creator:
Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
System:
The UNT Digital Library
Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders
The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas cooled graphite-moderated (GGBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date:
May 24, 1961
Creator:
Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
System:
The UNT Digital Library
A Parametric Study of a Gas Cooled Reactor
The results of a parametric study on a gas cooled reactor are reported on herein. The system considered was a helium cooled, UO2 fueled arrangement with the fuel assemblies consisting of clusters of long cylindrical elements, each element covered b a stainless steel jacket. The axial power distribution was assumed to be a "chopped cosine" having an axial peak-to-average power 1.32.
Date:
July 24, 1959
Creator:
Epel, L. G.
System:
The UNT Digital Library
Lecture Notes on Reactor Controls
This course on reactor controls is for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. This material is the outgrowth of the notes prepared for the lectures on Reactor Controls given in the Oak Ridge School of Reactor Technologu. The lectures given by T. E. Cole in 1953-1955 are the basis of portions of the subject matter on reactor kinetics. Many suggestions and ideas contributed by E. R. Mann are included throughout almost every section. In addition, several members of the Oak Ridge National Laboratory, and of the Reactor Controls Department in particular, have provided information which has been included in these lectures notes.
Date:
June 24, 1959
Creator:
Walker, C. S.
System:
The UNT Digital Library
The Equation of the Fusion Curve
A generalization of the Lindemann law is used in connection with the Murnaghan equation of state for a solid to derive theoretically the empirical Simon equation for the fusion curve. For the alkali metals it is shown that experimental values of the temperature exponent in the Simon equation are quantitatively compatible with the theoretical evaluation given, and, furthermore, that the theory can predict approximate values of the experiment, in practice.
Date:
May 24, 1955
Creator:
Gilvarry, J. J. (John James), 1917-
System:
The UNT Digital Library
Fundamentals of Glass-to-Metal Bonding. [Part] 5-A. Temperature and Pressure Dependence of the Wettability of Metals by Glass. [Part] 5-B. Reactions of Tantalum and sodium Silicate Glass. Technical Report No. 5
Part A. The major effort during the past year has been the construction of a suitable vacuum furnace for studying the effects of temperature and pressure on the wettability of metals by glass. A systems was completed that was capable of subjecting test combinations up to temperatures of 1400 degree C at a working pressure of 1 x 10(-5) mm. of Hg. Part B. A compound, identified by X-ray analysis as sodium meta tantalate (na2Ta2O6), was found at the interface between a sodium silicate glass and tantalum metal which had been heated in vacuum to 1000 degree C. thermodynamic calculations, followed by further experimental evidence, were used to determine the chemical reaction between tantalum and sodium silicate which resulted in the formation of Na2Ta3O6. the compound was synthesized by other methods, and its structure investigated.
Date:
June 24, 1955
Creator:
Fulrath, Richard M.; Mitoff, Stephan P. & Pask, Joseph A. (Joseph Adam), 1913-2003.
System:
The UNT Digital Library
Estimated Gamma Radiation Levels at Access Holes in the HRT Shielding
An estimate has been made of the gamma radiation levels at access holes in the HRT Shielding when the plugs have been removed to service or maintain the reactor. In every case the radiation level at the holes was greater than the maximum permissible exposure rate of 0.3 roentgens per week. The radiation through the holes can be attenuated to some extent by flooding the reactor cell up to the flange to be disconnected. However, shielding would still be required and it is more practical to provide a small additional shield thickness to compensate for the moderate attenuation that could be gained from flooding.
Date:
January 24, 1957
Creator:
Collins, C. W.
System:
The UNT Digital Library
Secondary Refrigerant for HRT Refrigeration System
The criteria for selection of an HRT secondary refrigerant system refrigerant to replace Freon-11 are given. The properties of Amsco which make it desirable are tabulated and it is compared with triethyl phosphate (the second choice) and Freon-11.
Date:
January 24, 1957
Creator:
Robertson, R. C. & McLain, Howard A.
System:
The UNT Digital Library
Railroad Commission of Texas Oil and Gas Division Annual Report: 1991, Volume 1
First part of an annual report of the Texas Railroad Commission's Oil and Gas Division providing background on the industry and the agency's activities, information related to the production of oil and gas, and data regarding production by field.
Date:
August 24, 1992
Creator:
Railroad Commission of Texas. Oil and Gas Division.
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1960
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1960, activities, growth programs, public relations, resources, organizational leadership, and other information about scouting programs.
Date:
March 24, 1961
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1959
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1959, activities, service, organizational leadership, and other information about scouting programs.
Date:
March 24, 1960
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961
The design status of the Experimental Fast Ceramic Reactor (EFCR) is described for the period up to October 31, 1961. The primary purpose of the facility is to study the dynamic behavior of a fast ceramic reactor, including the experimental demonstration of the effectiveness of the Doppler coefficient in limiting the power excursion following a rapid insertion of reactivity.
Date:
April 24, 1962
Creator:
Horst, K. M.
System:
The UNT Digital Library
Further Experimental Results on Natural Circulation Loop Performance at 1000 psia Under Periodic Accelerations
Experimental results on the effect of periodic acceleration on a natural circulation, 1000 psia, two-phase flow loop are presented, and related to the topic of marine reactor design. The initial results of this work were given previously in GEAP 3397.
Date:
October 24, 1960
Creator:
Quinn, E. P.
System:
The UNT Digital Library
Zirconium Alloys for Steam Service: a Preliminary Study
The fabricability, elevated temperature strength, steam corrosion resistance, and hydrogen pickup of various binary, ternary, and quaternary alloys were studied experimentally.
Date:
June 24, 1960
Creator:
Klepfer, H. H.
System:
The UNT Digital Library
Enclosure Section of the Hazards Summary Report for the Dresden Nuclear Power Station
The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site near the confluence of the Kankakee and Des Plaines Rivers in Grundy County, Illinois, about 47 miles southwest of Chicago. The plant will be known as the Dresden Nuclear Power Station, and will employ a nuclear reactor of the dual-cycle boiling water type.
Date:
January 24, 1957
Creator:
Commonwealth Edison Company
System:
The UNT Digital Library
High-Thermal-Conductivity Fin Material for Radiators
This report is the result of a study to develop heat-resistant fin materials possessing a high thermal conductivity for air radiators. Since an economical and commercially feasible product was desired, the investigation was restricted primarily to a study of electroplated copper, clad copper, and copper alloys. Sheet material 0.008 to 0.010 in. thick was evaluated for fabricability and for metallurgical stability and thermal conductivity at 1500°F. From the results of the rests it was concluded that: (1) electroplates were unsatisfactory; (2) clad-copper fins possessing a thermal conductivity of 50% of that of copper are commercially feasible; (3) copper-aluminum alloys possessing a thermal conductivity approaching that of copper at 1500°F are possible. Service tests of clad copper and the copper-aluminum alloys indicate that the choice of materials will be dictated by the requirements of the radiator, since each presents some unique problems.
Date:
January 24, 1957
Creator:
Inouye, H.
System:
The UNT Digital Library
Thorex Thorium Nitrate Product Specifications
Activity and ionic impurity specifications are presented for Thorex thorium nitrate products. Two sets of specifications are given, one set for direct handling during refabrication of production reactor thorium metal slugs and the second for refabrication of future power reactor thorium metal elements by semi-remote technics. Consideration was given to the health hazard problems associated with each process step between the Thorex process and final refabricated source material in order to arrive at these specifications.
Date:
May 24, 1956
Creator:
Arnold, E. D. & Wischow, R. P.
System:
The UNT Digital Library
Bulk ThO2, a Reactor Material
Thorium, a fertile material, is of interest to the Reactor Program in the production of U233. Thorium can be extracted and processed to a very pure bulk metal for fabrication into solid fertile elements. There are advantages, technical and economic, for using fabricated bulk thorium dioxide rather than the metal in some applications. It is the purpose of this paper to point out these advantages and to present briefly the technology related to fabrication, radiation damage and chemical processing of ThO2.
Date:
May 24, 1956
Creator:
Johnson, J. R. & Warde, J. M.
System:
The UNT Digital Library
Determination of Corrosion Products and Additives in Homogeneous Reactor Fuel III. Polarographic Determination of Iron(III)
An ion-exchange -- polarographic method was developed for the determination of iron(III) in Homogeneous Reactor Fuels. Copper, which interferes, is removed from the fuel by plating it onto a cadmium coil. Iron is oxidized to iron(III) by potassium permanganate, and the iron(III) is separated from interfering metal ions by ion exchange on a Dowex 1 resin column that is in the sulfate form. The iron(III) in the effluent is determined polarographically in 0.5 M sodium citrate solution as supporting electrolyte. A fairly well defined polarographic wave is obtained for the iron(III) → iron(II) reduction at a half-wave potential of approximately -0.15 v. vs. the S.C.E. The relative standard deviation of the data for 2 µg of iron(III) per ml of solution in the polarographic cell was 6.5%; for 10 µg of iron(III) per ml it was 0.6%.
Date:
October 24, 1955
Creator:
Horton, A. D.; Thomason, P. F. & Raaen, H. P.
System:
The UNT Digital Library
Electronuclear Research Division Semiannual Progress Report For Period Ending March 20, 1955
The ORNL 86-in. cyclotron is being modified to provide for deflection of the proton beam. It is expected that operation will be resumed late in the spring. Nuclear physics work was limited, for the most part, to interpretation of previously collected data and to making preparations for utilizing the deflected beam. It was found that for certain isotopes the production rates could be almost doubled by operating at a slightly reduced energy and a much larger current. With the use of the ORNL 63-in. cyclotron, the absolute values of the electron capture and loss cross sections for 26-Mev nitrogen ions were obtained. The angular distribution of the cross sections for elastic scattering of nitrogen by nitrogen was measured at energies from 13 to 22 Mev. A double-focusing 90-deg magnet is being planned for use in identifying stable reaction products from nitrogen-induced reactions. The major components of the revised 44-in. test cyclotron were assembled and are being tested. Consideration is being given to the use of these components, along with a new 20,000-oersted magnet and a shielded cyclotron room, and if the tests are satisfactory the Laboratory will have available a machine which will accelerate N5+ ions to 81 Mev.
Date:
June 24, 1955
Creator:
Livingston, Robert S. & Howard, F. T.
System:
The UNT Digital Library
Termination Report for Development Test IP-306-K Spline Coilers at K Reactor
A reliable spline disposal system is necessary for full utilization of the Poison Spline Control System. The spline choppers were not reliable enough so a spline coiler was developed and designed to replace the choppers. A Development Test, IP-306-X (HW-63820), was issued authorizing on-pile testing of the spline coiler at X area. This report closes the Development Test and discusses the use of spline coilers.
Date:
June 24, 1960
Creator:
McCarthy, P. B.
System:
The UNT Digital Library