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Southwest Retort, Volume 12, Number 6, February 1960

Description: This publication of the Dallas-Fort Worth Section of the American Chemical Society includes information about research, prominent scientist, organizational business, and various other stories of interest to the community. Published monthly during long academic semesters.
Date: February 1960
Creator: American Chemical Society. Dallas/Fort Worth Section.
Partner: UNT Libraries
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EURIPUS-3 AND DAEDALUS--MONTE CARLO DENSITY CODES FOR THE IBM-704

Description: EURIPUS-3 calculates the one-dimensional spatial density of neutrons slowing-down past a given energy in an infinite homogeneous medium consisting of hydrogen and one other isotope with arbitrary mass and energydependent differential-elastic and absorption cross sections. DAEDALUS determines the corresponding spatial distribution of angular integrals of an arbitrary function times the vector flux density. Spatial moments of all density functions are furnished directly. Although scattering angles are calculated by Monte Carlo, the spatial distributions and, in DAEDALUS, the energy distribution are obtained partly from an analytic treatment which, besides saving tinne, enables the output to be in the form of actual density functions at specified planes and energies, rather than histograms covering finite intervals. At certain steps in the computation of both the spatial and energy distributions, part of the analytic treatment is replaced by Monte Carlo in order either to maximize efficiency and/ or to avoid round-off error. The neutron source may be monoenergetic with either isotropic or monodirectional angular distributions, or else the source may be that from deuterons bombarding deuterons. The volume displaced by a cylindrical tube from an accelerator to the source can be accounted for in the neutron first flight but not thereafter. (auth)
Date: February 1, 1960
Creator: Amster, H. J.; Kuehn, H. G. & Spanier, J.
Partner: UNT Libraries Government Documents Department
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Preliminary Design and Hazards Report-Boiling Reactor Experiment V (BORAX V)

Description: From introduction: "The report is preliminary. At the time of writing, the status of the BORAX V project is that design of the reactor buildings and plant, done in collaboration with the architect-engineer with the architect-engineer has been completed and construction has just started; however, the mechanical design of the fuel and cores is still tentative."
Date: February 1960
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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THE DIFFUSION OF KRYPTON-85 FROM URANIUM DIOXIDE POWDER

Description: The diffusion of Kr/sup 85/ in two UO/sub 2/ powders was studied by performing a series of post-irradiation anneals on the powders. The emanation data were analyzed by considering the effect of sintering as well as the effect of a distribution of particle sizes within the sample. Measurements were made at 900 to 1500 deg C. The time at a temperature was between 8 and 24 hours. The diffusion coefficients for Kr/sup 85/ in the two powders are represented by the equations: D = 2.65 x 10/sup -4/ exp - 65,500/RT for UO/sub 2/ prepared from crushed UO/sub 2/ pellets and, for a chemically prepared UO/sub 2/ powder, D = 4.9 x 10/sup -4/ exp - 73,800/RT. (auth)
Date: February 1, 1960
Creator: Auskern, A.B.
Partner: UNT Libraries Government Documents Department
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Transistor Counting Systems for Scintillation Detectors

Description: The requirements for multiple-coincidence counting systems with 10{sup -8}- to 10{sup -9}-sec time resolution can be met economically with presently available high-frequency transistors. The design of solid-state coincidence circuits, amplitude discriminators, and decade scalers is considered and their operation discussed. Several systems have been designed utilizing up to 180 channels from scintillation detectors.
Date: February 17, 1960
Creator: Baker, Stanley C.; Jackson, Horace G. & Mack, Dick A.
Partner: UNT Libraries Government Documents Department
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Organic Compounds in Fission Reactors. [Part] 2. Thorio-Organic Compounds

Description: The advantages of the use of organic liquids in fission reactors to minmize corrosion and pressure problems were studied relative to the solution of thorium in such fluids. Thorio-organic compounds were prepared from organic acids, diketones, and other chelating compounds. Salts of carboxylic and phospho- organic acids were insoluble. The chelate with dibenzoylmethane was soluble in molten biphenyl but was decomposed at 300 deg C. The general low solubility of thorio-organic compounds in nonpolar solvents can be explained by steric effects. The large thorium atom has the ability to form strong coordination complexes with adjacent molecules, leading to coordination polymers. The effect can be minimized by shielding the thorium nucleus with large organic groups such as dibenzoylmethane. The large, branched organic groups needed to impart solubility limit the maximum solubility. (auth)
Date: February 29, 1960
Creator: Baldwin, W. H.
Partner: UNT Libraries Government Documents Department
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A versatile recording potentiometer

Description: ABS>A recording potentiometer was modified to provide a versatile instrument that can be applied to a variety of problems without time-consuming changes. Ranges may be selected in six spans, from 0.5 to 100 mv. No adjustments of amplifier gain are required when switching from one range to another. Zero suppression is continuously variable over a plus or minus 100 mv range by means of coarse and vernier controls. Cold junction compensation is provided for four standard thermocouples, and chart speeds from 1/2 to 16 im- ./ hr may be selected at will. (auth)
Date: February 1, 1960
Creator: Ballou, C. O.
Partner: UNT Libraries Government Documents Department
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Examination of a Nonregenerative Heat Exchanger From the u.s.s. Nautilus (Ssn-571)

Description: Selected components from a staianless steel nonregenerative heat exchanger removed from the U.S.S. Nautilus (SSN571) have been examined for evidence of stress-corrosion cracking. The examination was conducted on three baffle plates, all primary-face seal welds, and the tubes and the surrounding tube sheets of 7 out of a total of 35 tubes. Maximum operating temperature of the heat exchanger was 260 ction prod- F for the inlet primary water and 164 ction prod- F for the exit secondary water. Chloride content of the secondary water averaged 5 ppm, with a maximum of 15 ppm. Only one suspected stress-corrosion crack was found in the components normally in contact with the secondary water. The crack, 2.5 mils in depth, was located on a fully exposed tube. At the 95 per cent confidence level this represented a probability of finding cracking on fully exposed surfaces in 0 to 60 per cent of the rest of the tubes in the heat exchanger. Severe stress-corrosion cracking was found in tubes in the tube-sheet drain area at the juncture with the inner tube sheet at the inlet end, where secondary water seeped past the expanded tubes. Cracks were detected in five of seven tubes for a statistical probability of 25 to 96 per cent at the 95 per cent confidence level. Maximum depth of cracks was 28 mils or 80 per cent penetration of the 35-mil-thick tubing wall. Stress-corrosion cracks also were found around several holes on the drain-side tube-sheet surfaces at the inlet end. Maximum depth was 12 mils, which did not seriously threaten penetration of the 9/16-in.-thick tube sheet. Cracks were detected in 5 of 35 primary-face seal welds at the inlet end and in 11 of 35 at the outlet end. This behavior was attributed to hot-short cracking of the Type 347 stainless …
Date: February 19, 1960
Creator: Berry, W. E.; Stewart, O. M. & Fink, F. W.
Partner: UNT Libraries Government Documents Department
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REDUCTION OF CUPRIC OXIDE BY HYDROGEN. II. CONVERSION OF HYDROGEN TO WATER OVER FIXED BEDS

Description: The conditions under which hydrogen could be quantitatively recovered from mixtures of gases by oxidation over fixed beds of CuO were investigated. The conversion of H/sub 2/ to H/sub 2/O by reduction of CuO in fixed beds increased with in- creasing bed length, temperature, hydrogen/argon ratio, and decreasing mesh size of CuO. Residence times required for 99% conversion in a 1- in.-diam. bed were 0.6 and 1.2 sec for 30% hydrogen-70% argon and 10% hydrogen90% argon mixtures, respectively, at a total gas flow of 1 l/min. The CuO used was 25-mil-diam. wires with a surface area of 0.019 m/sup 2//g. The residence time required for a given value of conversion decreased about 10% when the total flow rate was increased from 1 to 1.7 liters/min, which indicates that the reduction is mass-transfer controlled to a slight extent under the experimental conditions used. (auth)
Date: February 12, 1960
Creator: Bond, W.D. & Clark, W.E.
Partner: UNT Libraries Government Documents Department
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Recommendations to apply the ``square pile`` total control concept

Description: It is recommended that the ``square pile`` concept be adopted for all disaster total control calculations, and that the basic reactor constants listed in HW-62884, except for Ball 3X local strength at the DR Reactor, be used in applying this method. Curves are included for each reactor type, indicating allowable enrichment based on appropriate local control strengths. (The reactors whose operating methods are affected by disaster total control requirements are B, D, F, and DR Reactors; the remaining piles have sufficient geometrical coverage). An example of the analytical method is included.
Date: February 25, 1960
Creator: Bowers, C. E.
Partner: UNT Libraries Government Documents Department
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Summary of Corrosion Investigations on High-Temperature Aluminum Alloys. Period Covered : February 1955-October 1956

Description: Tests were performed on aluminum alloys to evaluate their behavior in high-temperature, high-pressure. watercooled and -moderated nuclear reactor enviromnents. Test equipment, sample preparation. and test procedures are discussed. Aluminum nickel alloys were found resistant to disintegration for periods up to 60 days in dynamic water at 600 ction prod- F. The corrosion rates of the aluminum alloys M-388 and X-2219 at 600 ction prod- F were found to be too high to merit consideration for cladding materials. The influence of pH. gas content, and velocity of the water on the corrosion of the above alloys was evaluated. Hydrogen addition at startup appeared to increase the degree of corrosion attack on the M-388 alloy. Irradiation tests on aluminum-nickel alloys revealed that the corrosion rate increased with distance from core. In-reactor samples of M-388 exhibited less corrosion attack than out-of-reactor samples. Boiling water corrosion tests were performed on M-388 for 1612 hr at 422 ction prod- F with an average heat flux of 25,000 Btu per hrft/sup 2/. The over- all corrosion rate was 2.9 mil per yr. It is concluded that the corrosion rate of M-388 is acceptable for the specified test conditions: (1) absence of radiation: (2) demineralized water at 422 ction prod- F; and (3) heat transfer rates not exceeding 40,000 Btu per ft/sup 2/. No accelerated corrosion attack due to boiling heat transfer and no significant buildup of corrosion products on heat transfer surfaces were noted. Accelerated corrosion of M-388 was noted when coupled with Type 304 stainless steel and exposed to tap water at room temperature, or air-saturated, demineralized water at 680 ction prod- F. A technique for stripping corrosion films from aluminum and aluminum-nickel alloys is given. (C.J.G.)
Date: February 1, 1960
Creator: Breden, C. R. & Grant, N. R.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Progress Report: May-October 1959

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 10, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Partner: UNT Libraries Government Documents Department
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A Compendium of Information for Use in Controlling Radiation Emergencies: Including Lecture Notes from a Training Session at Idaho Falls, Idaho, February 12-14, 1958

Description: From introduction: This report is a summary of the lecture material in the training course held at Idaho Falls, Idaho, to familiarize members of radiological assistance teams with information helpful in the response to an unusual accident including release of radioactive materials to a populated environment.
Date: February 1960
Creator: Brodsky, Allen & Beard, G. Victor
Partner: UNT Libraries Government Documents Department
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RADIOMETRIC METHODS FOR THE DETERMINATION OF MAGNESIUM AND CALCIUM IN PORTLAND CEMENT

Description: Radiometric methods of analysis for magnesium and calcium have been developed as part of a program for the U. S. Atomic Energy Commission. Office of Isotopes Development, which are applicable to the determination of these elements in portland cement Both methods employ, as a precipitant, a standard solution of (NH/sub 4/)/sub 2/HPO/sub 4/ labeled with phosphorus-32. In the presence of NH/ sub 4/OH, this reagent precipitate; MgNH/sub 4/PO/sub 4/ or Ca/sub 3/(PO/sub 4/)/ sub 2/ from a solution of magnesium or calcium ions. The reduction in the radioactivity level of the labeled phosphate solution after precipitation serves as a measure of the phosphate reacted and thus a measure of the quantity of magnesium or calcium present. Studies have been made of the effects of reagent concentration, NH/sub 4/OH concentration, and other experimental variables. The interference of other elements present normally in portland cement and its raw materials has been determined. The concentration ranges for highest accuracy have been found to be 5 to 15 mg of MgO per 100 ml and 15 to 30 mg of CaO per 50 ml. (auth)
Date: February 18, 1960
Creator: Brown, C.T.; Howes, J.E. Jr.; Elleman, T.S.; Townley, C.W. & Sunderman, D.N.
Partner: UNT Libraries Government Documents Department
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Production of cobalt-60

Description: Cobalt samples frequently are irradiated in nuclear reactors to produce gamma sources and can be irradiated as integral flux monitors because of the long half-life of the isotope produced. At the present time a small cobalt sample is being irradiated within the KW Reactor Snout facility for future use as a radiographic source for inspection of finished product in the Chemical Processing Department. Analysis was made to estimate the buildup of activity in this sample; the general equation may be of interest and value for other cobalt sample irradiations.
Date: February 29, 1960
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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Magnetic Recorder for Nuclear Pulse Application : Covering the Period from December 6, 1959 to February 5, 1960

Description: "Abstract: An evaluation of a modulator flux sensitive playback head to be used with an analog magnetic recorder for nuclear pulse information storage was made. The modulator head was found unsultable. A pulse stretching unit was constructed which takes pulses from a standard linear pulse amplifier and provides an output signal suitable for driving a recording head."
Date: February 24, 1960
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
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MAGNETIC RECORDER FOR NUCLEAR PULSE APPLICATION. Period covered: December 6, 1959 to February 5, 1960

Description: An evaluation of a modulator flux sensitive playback head to be used with an analog magnetic recorder for nuclear pulse information storage was made. The modulator head was found unsultable. A pulse stretching unit was constructed which takes pulses from a standard linear pulse amplifier and provides an output signal suitable for driving a recording head. (For preceding period see ARF-1151- 3.) (C.J.G.)
Date: February 24, 1960
Creator: Burgwald, G.M. & Norton, R.M.
Partner: UNT Libraries Government Documents Department
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Radial Temperature Profile of Sodium Pool Boiling Heater Assembly

Description: The radial temperature around a sodium reactor heater assembly submerged in water is calculated using a model of the heater cross section found by conformal mapping. Thermocouple readings were also analyzed. When the heat flux is 5 x 10/sup 5/ Btu/hr-ft/sup 2/, a radial temperature drop of about 680 deg C across the center of the thermocouple well is calculated and found to be within 6% of the experimental value. Since most of this drop is across the 0.001-in. helium gap between the heater and its sleeve, it is concluded that the thermocouple will have to be bonded to the sleeve for dependable reading of true sleeve temperature. Drawings of the heater assembly and thermocouple are given. (D. L. C.)
Date: February 22, 1960
Creator: Cappel, H. H.
Partner: UNT Libraries Government Documents Department
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The Use of Ultrasonic in Electrodeposition and Electroplating : a Bibliography

Description: This bibliography contains 20 references on the use of ultrasonic in electrodeposition and electroplating. The bibliography is limited to the period 1955 to 1959, with the references arranged alphabetically by title. Sources used in compiling this bibliography were: Applied Science and Technology Index, ASM Review of Metal Literature, Chemical Abstracts, Industrial Arts, Index, Nuclear Science Abstracts.
Date: February 18, 1960
Creator: Cernak, Elizabeth A.
Partner: UNT Libraries Government Documents Department
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Maximum Volume-to-Stress Ratio for a Two-Radii-Contour Diaphragm Pump

Description: Analytical methods were employed to determine the maximum volume-to- stress ratio for a two-radii-contour diaphragm pump. A proposed failure criterion considers the effect of biaxial stresses on fatigue failure through. the use of the Mises-Hencky criterion for fatigue failure. By use of the proposed criterion, it was determined that an optimunn ratio of the two radii does exist, its value being dependent on the ratio of diphragm thickness to diaphragm deflection. Values for the optimum ratio of the two radii (where the ratio of radii is defined as the radius of the central pcrtion of the diaphragm contour divided by the radius of the outer pontion of the diaphragm) range from 1.94 to 7.33 as the ratio of diaphragm thickness to diaphragm deflection varies from 0.5 to 0.05, respectively. (auth)
Date: February 15, 1960
Creator: Cheverton, R. D.
Partner: UNT Libraries Government Documents Department
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IMPROVED METHOD FOR PRECIPITATING MANGANESE DIOXIDE

Description: An improved method for precipitating manganese dioxide was demonstrated that significantly increases the allowable feed rate of the Purex head-end centrifuge. The effects of several process variables are discussed. (auth)
Date: February 1, 1960
Creator: Clark, H.J. Jr.
Partner: UNT Libraries Government Documents Department
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