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Chemistry Division Quarterly Progress Report for Period Ending September 30, 1950

Description: Technical report covering chemistry of source, fissionable, and structural elements, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, and instrumentation at the Oak Ridge National Laboratory for the period ending September 30, 1950. [From Abstract]
Date: March 1, 1951
Creator: Taylor, E. H.; Boyd, G. E. & Bredig, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Pilot Plant Section Report for November, 1950- January, 1951

Description: Technical report presenting a summary of the flowsheets, equipment, and progress for the Oak Ridge National Laboratory (ORNL) pilot plant development of the Purex Process and of the ORNL Metal Recovery Program. As of this report, conversion of the Purex pilot plant equipment in Buildings 3019 and 3503 is 90% complete. The building structure for the ORNL Waste Metal Recovery plant had been completed, and 15% of the process equipment had been installed. The first hot runs for this plant were sche… more
Date: March 8, 1951
Creator: Jackson, H. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Surface to Mass Dependence of Effective Resonance Integrals for Uranium 238 Cylinders

Description: Technical report outlining the determination of the effective resonance integral for U238 as a function of the mass ratio for cylinders of 5/8" to 3" diameter. Also gives a linear approximation of the effective resonance integral with infinite shielding in the form of a function. [From Abstract]
Date: March 20, 1951
Creator: Risser, J. R.; Arfken, G. B., Jr.; Cuykendall, T. R.; Stephenson, R. J. & Caldwell, D. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dry Fluoride Process Status Report

Description: Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [Fr… more
Date: March 27, 1951
Creator: Leuse, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Fluoride on the Corrosion of Stainless Steel in the Presence of Excess Al+3 Ion

Description: Technical report detailing corrosion tests of Type 347 stainless steel for two weeks in boiling uranyl nitrate, sulfuric acid media, with and without additions of Al+3 and F-1 in a 2:1 mole ratio. The results of these tests show that although the presence of aluminum greatly reduces the deleterious effect of fluoride, the corrosion rates are still three to four times greater than when no fluoride is present. [From Abstract]
Date: March 27, 1951
Creator: Olsen, Arnold R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry Division Quarterly Progress Report for Period Ending January 10, 1951

Description: Technical report covering experiments happening on the Analytical Chemistry Division's sites at the Oak Ridge National Laboratory. Includes information on ionic analyses, radiochemical analyses, spectrochemical analyses, service analyses, inorganic preparations, analytical chemical control of homogeneous reactor solution, optical and electron microscopy, and service analyses. [From Abstract]
Date: March 28, 1951
Creator: Kelley, M. T. & Susano, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mathematics Panel Quarterly Progress Report for the Period Ending January 31, 1951

Description: Technical report outlining the construction progress of the Oak Ridge digital computer at Argonne. Included is the schedule of events for the Mathematical panel and programs during the presentation of contributed papers for the Biometric Society [From Summary]
Date: March 30, 1951
Creator: Householder, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending December 10, 1951

Description: This quarterly progress report details the ongoing research and experiments at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. The first part of this report discusses reactor theory and design. The second part of this report is not included. The third part of this report discusses materials research. The fourth part of this report includes appendixes
Date: March 6, 1952
Creator: Briant, R. C. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Solution of Experimental Breeder Reactor Slugs

Description: From abstract: "A full-scale, always-safe, metal dissolver for Experimental Breeder Reactor fuel was designed, built, and installed for test operation. It was found that the dissolver operated satisfactorily, and feasible operating procedures were established for the dissolution of bare, or jacketed, EBR slugs. Minor modifications of the dissolver design have been required to accomodate [sic] a modified EBR slug, but it is believed that this will not significantly affect its operating character… more
Date: March 11, 1952
Creator: Sampson, E. M., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Damage to Organic Ion-Exchange Materials

Description: From abstract: "The stability of polystyrene and phenolic ion-exchange resins to radiation from a Co60 source and from absorbed Ce144-PR144 was investigated. Sulfonated polystyrene cation-exchange resins lost 10 to 20% of their capacity per watt-hour of radiation absorbed per gram of oven-dry resin, while the quaternary amine anion-exchange polystyrene resins lost about 40%. Phenolic cation-exchange resins lost only 1%."
Date: March 16, 1953
Creator: Higgins, I. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mathematics Panel Semiannual Progress Report

Description: From July through December, a total of 1750 hr of computer time was used by programmers in "debugging" and in running problems. With the acquisition of a second operator, the evening shift was initiated. A night-shift operator is presently being trained, and third-shifts operations will probably begin after completion of the magnetic-tape memory. / Engineering time is regularly scheduled for 4 hr each morning and 1/2 hr late in the afternoon. An electronic technician is on duty during evening-s… more
Date: March 2, 1955
Creator: Householder, A. S. & Sangren, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1955

Description: This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and other ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into three major parts: I. Reactor Theory, Component Development, and Construction, II. Materials Research, and III. Shielding Research. The ANP Project is comprised of about 530 technical and scientific personnel engaged in many phases of rese… more
Date: March 12, 1956
Creator: Jordan, W. H.; Cremer, S. J.; Miller, A. J. & Savelainen, A. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fission Product Activities in Irradiated Natural Uranium, Enriched Uranium, and Thorium

Description: Calculated data and graphs describing the effects of batch thermal-neutron irradiations on the buildup of fission products in natural uranium, enriched uranium, and thorium are presented together with empirical equations and plots correlating total fission product activities and/or decontamination factors. Fluxes of 1012-1015 are considered.
Date: March 28, 1956
Creator: Arnold, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952

Description: From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ pa… more
Date: March 7, 1957
Creator: Livingston, Robert S. & Howard, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Sodium Hydroxide - Sodium Hydride System

Description: Portions of the NaOH-NaH phase diagram were studied by means of differential thermal analysis. Under certain conditions NaH will either react with NaOH according to the equation NaH + NaOH in equilibrium Na/sub 2/O + H/ sub 2/ or thermally dissociate according to the equation NaH in equilibrium Na + 1/2 H/sub 2/. Both of these reactions are suppressed by a high H/sub 2/ pressure; and NaH neither reacts nor dissociates to an extent sufficient to affect the results reported. This was evidenced by… more
Date: March 7, 1957
Creator: Kerzner, Marvin S.; Kelly, Henry C. & Johnson, Sidney
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Sodium Hydroxide - Sodium Oxide - Sodium - Sodium Hydride - Hydrogen System

Description: Sodium hydride dissolves in and reacts with molten NaOH to give an equilibrium mixture of NaH, NaOH, Na/sub 2/O, Na, and H. In the case where there is a gaseous phase (hydrogen) and only one condensed phase, the system is defined by the temperature, pressure, and one composition variable. The equilibrium, H/ sub 2/ pressure, which is a measure of the H/sub 2/ activity within the melt, was determined as a function of the composition of the condensed phase(s) at 600, 700, and 500 deg for equilibr… more
Date: March 7, 1957
Creator: Kelly, Henry C.; Sullivan, Edward A. & Johnson, Sidney
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Volatility Pilot Plant : Design of a NaF Packed Tower for Removing HF from Fluorine

Description: A 4-ft-7-in. adsorption column packed with 1/8 in. sodium fluoride pellets was designed to reduce the hydrogen fluoride content of the fluorine being used by the Volatility Pilot Plant from 5% to less than 0.01%. It will be a non-isothermal packed bed with the bas inlet heated to 100 C to avoid plugging and the exit cooed to 25 C for more complete HF removal.
Date: March 7, 1957
Creator: Watson, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Slurry Loop Program

Description: The in-plie slurry loop work is now being considered as a joint program between the PAR project and ORNL. It is proposed that PAR design, fabricate and test the in-pile loops and that ORNL operate the loops in-pile, dismantle the loops after irradiation and made the appropriate measurements to determine the radiation effects. This report gives the objects of the slurry in-pile program and outlines the facilities and operations required to execute ORNL's part of this program.
Date: March 8, 1957
Creator: Arehart, T. A.; Compere, E. L. (Edgar L.); Ferguson, D. E.; Korsmeyer, R. B. & McBride, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Semipermanent Freeze Plug Tests for HRT-CP

Description: Five uninsulated semipermanent freeze coils, series connected, can be frozen when submerged in 70 F water with a Freon-11 flow rate of 1.85 gpm at an inlet temperature of -40 F. The refrigeration unit of the HRT-CP is capable of delivering >3 gpm to a similar semipermanent freeze coil system located in Cell C. Therefore the number of F-11 risers required in Cell C of the HRT-CP can be minimized by series connecting this many semipermanent freeze coils where required.
Date: March 11, 1957
Creator: Winget, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutron and Gamma-Ray Attenuation for a Fission Source in Water : Comparison of Theory with LTSF Measurements

Description: Calculations are presented of the fast neutron dose rate, the gamma-ray dose rate, and the thermal neutron flux along the source plate axis in the Lid Tank with the tank filled entirely with water. These calculations are compared with experimental measurements. The calculations are absolute and are compared with absolute measurements.
Date: March 12, 1957
Creator: Otis, David Ridgway
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High-Temperature Properties in Relation to Design

Description: The essential physical and mechanical properties of materials which enter into the design considerations of high-temperature systems have been outlined, and the relationship of these factors to the detailed design of structural members noted. Particular attention is given to the phenomenon of strain-cycling and relaxation, and several engineering devices wherein these effects can markedly influence design are mentioned. Techniques and apparatus for the measurement of strain-cycling and relaxati… more
Date: March 14, 1957
Creator: Weir, J. R.; Meghreblian, Robert V. (Robert Vartan) & Douglas, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TBP Stripping in Bubble-Cap Column and Concomitant Product Evaporation

Description: A study was conducted to demonstrate the stripping and evaporation steps in a Purex-type uranium recovery process and to ascertain the operating behavior of the equipment under a range of conditions. The factors considered were control, effectiveness, and reliability of equipment and optimum feed point. Experimental procedures are described, and recommendations for equipment modifications are included. (J.R.D.)
Date: March 18, 1957
Creator: Long, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement of the Friction Characteristics for Flow in the ART Fuel-to-NaK Heat Exchanger

Description: The friction characteristics of a full-scale straight-tube model of the ART fuel-to-NaK heat exchanger were determined experimentally. The presence of the spacers resulted in a transition to semi-turbulent flow at a Reynolds modulus of 350. this semi-turbulent flow persisted up to a Reynolds modulus of 5,000. The circumferential spacers were found to contribute slightly more than the radial spacers to the pressure loss in the heat exchanger.
Date: March 19, 1957
Creator: Cohen, S. I. & Jones, T. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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