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Effects of Heat Treatment on Microstructure and Fabricability of 48 wt % Uranium - 52 wt % Aluminum Alloys

Description: It has been reported in the literature that prolonged soaking of 16 wt & uranium-aluminum alloys at elevated temperatures induces a microstructural changed termed "conglobulation". this process is essentially a spheroidization of the UAl4 eutectic. Conclusions of the tests: (1) Extended soaking of 48 wt $ uranium-aluminum alloy billets at 600 C does not improve their hot-rolling characteristics. (2) Soaking periods of 50 hours and greater reduce the tensile and yield strengths of these alloys.… more
Date: March 15, 1957
Creator: Thurber, William C.
Partner: UNT Libraries Government Documents Department
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Acid Formation in the Radiolysis of Phosphorus Esters

Description: The radiolytic decomposition of tributyl phosphate has been show by burr to product gases, acids, and polymers. the acids that are formed can limit the usefulness of tributyl phosphate for the processing of radioactive materials. The study of acid formation on radiolysis therefor becomes important to us for the understanding of the mechanism of acid formation, the influence of added materials and the effect of the structure of organo- phosphorous compounds. Samples of purified esters have been … more
Date: April 3, 1957
Creator: Baldwin, W. H.
Partner: UNT Libraries Government Documents Department
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Suggestion for High Pressure Letdown Device

Description: A letdown valve design is described which reduces erosion of the sealing surfaces. It also provides for water flushing of the sealing surface before closing.
Date: April 2, 1957
Creator: Lyon, Richard Norton
Partner: UNT Libraries Government Documents Department
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Pressure Rise in HRT Shield Due to Reactor and Replacement heat Exchanger Rupture

Description: .Recalculations were made of HRT cell pressures in the event of a simultaneous rupture of the reactor core vessel and the fuel and blanket heat exchangers. These calculations will be applicable after the replacement fuel heat exchanger is installed. The pressure rise in the cell is plotted as a function of time. A maximum cell pressure of 34 psig is achieved ~7 sec after rupture.
Date: April 2, 1957
Creator: Bolger, J. C.; Maak, R. O. & Gift, E. H.
Partner: UNT Libraries Government Documents Department
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A Preliminary Study of Molten Salt Power Reactors

Description: A preliminary study of molten salt power reactors was made. The most promising fuel carrier salts were the fluorides and chlorides of the alkali metals, zirconium, and beryllium. The chlorides were found to have lower melting points but were less stable and more corrosive than the fluorides. A Li/sup 7/ F- - BeF/sub 2/ mixture with ThF/sub 4/ and UF/sub 4/appeared to perform best. Of the numerous alloys tested as container material, Inconel and a nickel-- molybdenum alloy INOR-8 appeared to be … more
Date: April 29, 1957
Creator: MacPherson, H. G.; Alexander, L. G.; Carrison, D. A.; Estabrook, J. Y.; Kinyon, B. W.; Mann, L. A. et al.
Partner: UNT Libraries Government Documents Department
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Second and Third Operating Test of HRT Core Vessel Transition Joint and Expansion Bellows Mockup

Description: Second and third tests were conducted on an expansion bellows and Zircaloy-stainless steel transition joint assembly, duplicating that used in the core-pressure vessel assembly of the HRT. The assembly was exposed for 1140 hours in the second test and and 167 hours in the third to a solution containing 0.04m UO2SO4, 0.02m H2SO4, and 0.005m CuSO4 in a 100A dynamic corrosion loop under conditions simulating reactor startup, shutdown, and steady-state operation. Results indicated that the transiti… more
Date: April 30, 1957
Creator: Greeley, R. S.; Ulrich, W. C.; Savage, H. C.; Griess, J. C. & Mauney, T. H.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Corrosion Group for the Period Ending April 30, 1957

Description: A third test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel was completed. No additional mechanical deflections of the bellows were made, but 12 additional thermal cycles of the unit were carried out. . The joint and bellows functioned properly and were leak-tight. Corrosion of stainless steel in 0.04 m UO2SO4 containing equimolar beryllium sulfate was not greater at 10-15 fps and much less at 15-75 fps, than in HRT solution at 200 and 225 C. … more
Date: April 30, 1957
Creator: Griess, J. C.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Partner: UNT Libraries Government Documents Department
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Curve Plotting Routine for the Oracle

Description: A general program has been written to plot curves on the Oracle curve plotter. A description of the code and complete instructions for preparation of input tapes and operation of the code are given. The code tape is available from the Mathematics Panel or from the author.
Date: April 11, 1957
Creator: Lietzke, M. P.
Partner: UNT Libraries Government Documents Department
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Supplement to: Curve Plotting Routine for the Oracle (57-4-56)

Description: A general program has been written to plot curves on the Oracle curve plotter. The supplement includes changes to slow down some of the loops and minimize the possibility of read-around errors and changes to handle special cases.
Date: October 22, 1957
Creator: Lietzke, M. P.
Partner: UNT Libraries Government Documents Department
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Temperature Effects on the Measurement of Aqueous Liquid Level by the Differential Pressure Method and Recommendations for Placement of Taps on the HRT Replacement Heat Exchanger

Description: Increasing temperature in an aqueous liquid system results in a decrease in liquid density and an increase in vapor density. When level is measured by the differential pressure method, temperature increase results in a decrease in the effective span f the instrument and a shift in zero. When the instrument reference leg is uncompensated, both zero and span shifts occur with the effects being most pronounced at the high levels. When the reference leg is compensated, zero shifts are eliminated (i… more
Date: April 26, 1957
Creator: Moore, R. L.
Partner: UNT Libraries Government Documents Department
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The Choice in Thorium Oxide Slurries for the Prevention of Caking in Circulating Systems

Description: A qualitative theory for cake formation in ThO2 slurries is presented. The sphere formation which occurs in "Standard" slurry can be explained on the same basis. The irregular and unpredictable yield strength is easily fitted into the theory. On the basis of this theory, the writer has been led to the conclusion that only colloidally stable slurries, or slurries with crystallites or comminution-resistant particles which are large enough to overcome colloidal effects (probably larger than 0.1u) … more
Date: April 22, 1957
Creator: Lyon, R. N.
Partner: UNT Libraries Government Documents Department
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Possible Radiation Damage to the Stator Windings of the HRT Circulating Pump

Description: A study of the degree and effects of radiation damage to the motor winding of the HRT 400-! canned motor circulating pumps was made. With the gamma flux estimate and the available radiation damage data, the effective life of the stator windings was estimated to be about one year, for normal operation of the pump and motor.
Date: April 80, 1957
Creator: Gift, E. H.
Partner: UNT Libraries Government Documents Department
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Report of Slurry Blanket Test Run SM-2

Description: Run SM-2 was run to determine whether a sulfated ThO2 slurry could be handled in a hydrodynamic system similar to the HRT test blanket. It was found that the ThO2 concentration circulating in the pipes was consistently 50% or less of the expected concentration based on the quantity of the oxide changed. The run lasted 1730 hours. It was terminated because of a slurry leak a few days before a shutdown had been scheduled. Severe erosion was found in the pump impeller and flow nozzle . Chloride co… more
Date: April 29, 1957
Creator: Parsly, L. J., Jr.; Falkenberry, H. L. & Miller, I. M.
Partner: UNT Libraries Government Documents Department
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Maintenance of Various Reactor Types

Description: This technical report presents an overview of nuclear reactor maintenance to be used in planning a nuclear reactor. There are certain basic maintenance fundamentals that are common to all types of reactors that may be' incorporated in a power producing facility. Basically, there are only two types of maintenance procedures. The direct type, which is common to conventional steam plants, may be used in some areas where the radioactivity is low enough. In most parts of the plant, maintenance will … more
Date: April 8, 1957
Creator: Draper, R. D.
Partner: UNT Libraries Government Documents Department
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Deflection Equations for Various Loading of Circular-Arc Curved Beams

Description: In analyzing stresses, deflections, and forces in piping and certain structural systems, it is useful to have a set of equations giving the deflections at any point of a curved beam in terms of the various loads acting on the beam. This technical report presents the deflection equations for a curved circular-arc beam of variable length. The cases treated include in-plane and out-of-plane bending due to forces and moments applied to the end of the beam in three principal directions, and uniforml… more
Date: April 22, 1957
Creator: Platus, D. L. & Greenstreet, B. L.
Partner: UNT Libraries Government Documents Department
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Thorium oxide Slurry Falling Ball Viscometer : Final Co-op Report, Winter, 1957

Description: A falling ball viscometer under development at ORNL, employing a flow system and an electromagnetically operated dash-pot pump, was evaluated for possible use with aqueous ThO2 slurry systems under reactor irradiation. Interchangeable check valve inserts were designed and fabricated to investigate several pump designs. Magnetic flux concentrations which originally prevented circulation of the ferritic stainless steel viscometer ball through the electromagnetic pump were eliminated by substituti… more
Date: April 10, 1957
Creator: Novak, P. E.
Partner: UNT Libraries Government Documents Department
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Operation of the Distillation Method for the Determination of Sodium Oxide in NaK During the Calibration of a Plug Indicator

Description: The distillation method (Argonne Sampler) for the analysis of sodium oxide in NaK was used to calibrate a plug indicator. The description of the equipment, procedure, and experiences with the Argonne Samplers are presented in great detail to aid future users of this method. Although this method is not very precise, it has been thoroughly checked out and is recommended as a standard means for sampling and analysis for oxide in liquid metal systems. (auth)
Date: April 30, 1957
Creator: Peak, R. D.
Partner: UNT Libraries Government Documents Department
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Possibility of Oxygen Depletion in Stagnant Uranyl Sulfate Lines

Description: It is concluded that an excess of O2 must be added to the HRT fuel circulating stream in amounts sufficient to recombine the D2 in dead-end lines and serve as corrosion protection.
Date: April 29, 1957
Creator: Gift, E. H.
Partner: UNT Libraries Government Documents Department
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HRP Dynamic Slurry Corrosion Studies : Quarter Ending April 30, 1957

Description: The assembly of a second thorium oxide slurry corrosion test facility, loop BS, has been completed and 2010 hr of operation on slurry have been logged. This second test loop has proved satisfactory from an .operational standpoint. Corrosion data and operational observations are given for six thorium oxide slurry runs made at 300 C in 100A pump loops BS and CS. A new development model of the rotator for an in-pile slurry toroid is described.
Date: April 30, 1957
Creator: Compere, E. L. (Edgar L.); Savage, H. C.; Reed, S. A.; Warner, R. M.; Ulrich, W. C.; Cole, H. D. et al.
Partner: UNT Libraries Government Documents Department
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Two-Group Analysis of Thermal, One-Dimensional, Multi-Region Spherical Reactors

Description: This technical report described the formulation of a set of two-group neutron diffusion equations and the solution for the critical fuel cross section in a one-dimensional, multi-region spherical reactor. A subsequent report will describe the ORACLE code developed for survey calculations using this method.
Date: May 1, 1957
Creator: Nestor, C. W.
Partner: UNT Libraries Government Documents Department
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Comments on the Transportation of Irradiated Fuel and Radioactive Wastes for M Louis Armand, Euratom Group

Description: General considerations involving the transportation of irradiated fuel and radioactive wastes are reviewed. It is assumed that many reactors will supply feed to a few large multipurpose chemical plants which ultimately send radioactive waste to a few disposal sites. General economic considerations of irradiated fuel reprocessing, economic aspects of the nuclear economy complex, growth predictions of the nuclear power economy in the U.S., general requirements for the shipment of fuel and waste, … more
Date: May 6, 1957
Creator: Culler, F. L.
Partner: UNT Libraries Government Documents Department
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A Brief Review of thermal Gradient Mass Transfer in Sodium and NaK Systems

Description: The fact that material transport does occur under conditions of finite temperature difference in a flowing molten metal system was established. The rate mass transfer was thought to be either diffusion limited or solution rate limited. It is believed that the mass transfer of structural materials in Na or NaK systems is solution rate limited. The limiting process has not been qualitatively or quantitatively confirmed for the Inconel-Na or Inconel-NaK system. Increasing the maximum system wall t… more
Date: February 11, 1957
Creator: DeVan, J. H. & West, J. B.
Partner: UNT Libraries Government Documents Department
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