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Absorption of Organic Acids on Thoria

Description: The adsorption of acetic and oleic acids on the surface of thoria was studied by means of infrared spectroscopy. An infrared analysis of the adsorbates before and after adsorption using differential double bean methods indicated that the adsorption of organic acids on thoria surfaces occurs by an esterification reaction between the organic acid and the hydroxylated thoria surface. Ammonia vapor will not adsorb on thoria, indicated the basic character of the hydroxylated surface.
Date: December 31, 1959
Creator: Bradford, Harold R. & Wadsworth, Milton E.
Item Type: Refine your search to only Report
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Annual Report of Research Progress

Description: This technical report constitutes a brief review of the work undertaken, entirely or in part, under the Contract AT(30-1)-1772 with eh United States Atomic Energy Commission. The work published during 1959 is listed at the end of this report and copies of the reprints or reports are attached where available. These investigations have been concerned with the examination of defect production and behavior as it may be observed by high frequency ultrasonic attenuation and velocity (modulus) changes… more
Date: December 31, 1959
Creator: Truell, Rohn, 1913-1968
Item Type: Refine your search to only Report
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Attempted Modification of Susceptibility of Tumors to X-Radiation : Final Report for August 1 1957 to August 31, 1959

Description: Attempts to secure a high degree of synchronization of cell division of the Krebs mouse ascites carcinoma, by combined use of aminopterin and citrovorum factor, and by use of colchicine and N-acetyl colchinol, were unsuccessful. In the course of the work, a new method for securing smears of ascites tumor cells was out, which we believe will be found useful
Date: December 31, 1959
Creator: Beck, Lyle Vibert, 1906-
Item Type: Refine your search to only Report
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for August 1959

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed by taking a macro photograph of the desired gradient by monochromatic (436 m mu ) light transmitted by the solution normal to the gradient in an appropriate diffusion cell. Two Druhm runs were terminated due to malfunction of the sodium metering system and the third run was terminated when the UF/sub 6/ nozzle ruptured. Calculations of particle temperature versus time relations for the flame denitration-cal… more
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Item Type: Refine your search to only Report
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Production test IP-262-A-11-FP, evaluation of projection fuel elements for use in ribbed process tubes: Demonstration loadings

Description: The objective of this test is to demonstrate the feasibility of projection fuel elements for use In existing process tubing and to determine the reduction in rupture rates or hot-spot incidence so achieved. This test is to authorize, (a) charging 20 columns of bumper type fuel elements and 20 columns of control elements per reactor into B, D, DR, F, and R Reactors for irradiation up to 1200 MWD/T exposure, and (b) irradiation of four columns each of enriched (0.947%) bumper and enriched (0.947%… more
Date: December 31, 1959
Creator: Hall, R. E.
Item Type: Refine your search to only Report
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Corrosion of INOR-8 and Inconel Dissolver Components of the Fluoride-Volatility Process

Description: The corrosion of INOR-8 and Inconel dissolver components used in the fluoride volatility process for the dissolution of zirconium with anhydrous HF in molten salts was investigated. Ten dissolution runs were made using simulated subassemblies formed from Zircoloy-2. The dissolver and components were made from INOR-8. Both the dissolver vessel and draft tube were examined several times during the series of runs. The solids which formed at different areas in the system were also analyzed. The res… more
Date: December 30, 1959
Creator: Fink, Frederick W.
Item Type: Refine your search to only Report
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Rupture Kinetics of Zircaloy-Clad Fuel Elements in High Temperature Water and Steam Interim Report 6 Effects of Carbon and Zirconium Content on Uranium Corrosion and Rupture Mechanism

Description: This is the sixth in a series of interim reports describing various phases of the study of fuel element rupture kinetics and mechanisms. Previous reports issued are: No. 1- Experimental Methods and Procedures, HW-61378, No. 2- Coextruded Rod Elements with Pinhole Defects, HW-61379, No. 3 - Mechanism of the Uranium-Water Reaction, HW - 61799, No. 4 Coextruded Tube Elements with Pinhole Defects and Various Annular Spacings, HW- 62348, No. 5- Comparison of In-Reactor and Ex-Reactor Ruptures, HW-62… more
Date: December 30, 1959
Creator: Troutner, V. H.
Item Type: Refine your search to only Report
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A Separated 1.17-Bev/c K- Meson Beam

Description: This report describes the design and testing of a 1.17-Bev/c separated K{sup -} beam designed in the fall of 1958 in connection with a 15-in. hydrogen bubble chamber experiment. At the target the K{sup -}/{pi}{sup -} ratio was 1/140. At the chamber, 4.0 K{sup -}-meson decay lengths from the target, and after two stages of electromagnetic separation, the K{sup -}/{pi}{sup -} ratio was 12.5, corresponding to a total pion suppression by a factor of about 10{sup 5}. The K{sup -} flux at the chamber… more
Date: December 30, 1959
Creator: Eberhard, Phillippe; Good, Myron L. & Ticho, Harold K.
Item Type: Refine your search to only Article
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Effect of Additions to Zircaloy on Hydrogen Pickup During Aqueous Corrosion

Description: An investigation was conducted into the possibility of alloy additions to Zircaloy-2 to diminish hydrogen absorption during aqueous corrosion. The nickel in Zircaloy-2 is believed to be the major constituent responsible for the relatively high hydrogen absorption. Additions of up to 0.5 wt.% antimony, arsenic, bismuth, or tellurium were selected on the basis of their known ability to poison the catalytic effects of nickel in hydrogenation reactions of other systems. Results of tests conducted f… more
Date: December 29, 1959
Creator: Berry, W. E.; White, E. L. & Fink, F. W.
Item Type: Refine your search to only Report
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Plant Expansion Task Force technical feasibility and R&D efforts

Description: The Expansion Study Task Force has evaluated several cases of Hanford reactor operation at power levels considerably higher than is presently obtained in the six older reactors. These higher power levels result in more rigorous operating conditions of temperature, heat flux, neutron flux, hydraulics, reactor control, etc. The purpose of this document, the various components of which were prepared by Process and Reactor Development Sub-Section personnel, is to assess the technical feasibility of… more
Date: December 29, 1959
Creator: Gilbert, W. D.
Item Type: Refine your search to only Report
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Prototype Freeze Trap Test

Description: A performance evaluation was made of a prototype liquid cooled freeze trap with sodium at 350 and 1000 deg F. The sodium freeze-off function was adequate for all test conditions encountered. The freeze-off occurred satisfactorily with the larger clearance provided by a test modification to provide 0.030 eccentricity to the rotating shaft. Turning the freeze-trap handle was successful in opening the unit for gas venting when 350 deg F sodium was used. For a seal formed with 1000 deg F sodium, 16… more
Date: December 29, 1959
Creator: Cygan, R.
Item Type: Refine your search to only Report
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Self-Shielding Cross Sections : a Bibliography

Description: This bibliography contains 37 references on self-shielding cross sections. The bibliography is limited to the period from 1951 through November 1959 with the references arranged alphabetically by title. The sources used in compiling this bibliography were: Abstracts of Classified Reports Nuclear Science Abstracts
Date: December 29, 1959
Creator: Cernak, Elizabeth A.
Item Type: Refine your search to only Report
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Net return course - operational severity index formuli

Description: This document presents a nomograph from which the relationship between reactor operating parameters, tube power, and outlet temperature can be correlated with rupture rate. The index indicates the severity of the reactor climate during irradiation and does not include the metal quality parameters defined in the rupture rate equation. The general form of the Operational Severity Index Equation is OSI=P{sup 3.3}/1000{times}t{sub 0}{sup 8.7}/100, where OSI, is the unitless Operational Severity Ind… more
Date: December 28, 1959
Item Type: Refine your search to only Report
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Development and Testing of an Improved Agitator for the Redox and Purex Separations Plants

Description: Relatively frequent agitator failures in HAPO Separations Plants have interfered with process continuity, contributed to process difficulties, and resulted in considerable maintenance expense. Predominantly the failures have been because of gear-reduction drive unit break-down or because of metallic fatigue and degeneration of the shaft-paddle assemblies. A simplified, slow-speed, direct drive agitator, previously described in HW-52755, proved to be quite durable and satisfactory during extende… more
Date: December 24, 1959
Creator: Dunn, J. & Sloat, R. J.
Item Type: Refine your search to only Report
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SM-2 REACTOR CORE AND VESSEL REVIEW REPORT FOR AUGUST 25, 1959 TO DECEMBER 14, 1959

Description: The most adverse power distribution was revised based on a comparison of PDQ calculations and measurements made during the SM-2 flexible experiments. A review of the basic nuclear data and calculational models employed in the SM-2 nuclear analysis was rnade. A comparison between initial reactivily, hot-to-cold reactivity change, and xenon reactivity with experiment was rnade. Based on a revised power distribution, the core flow requirement was reestimated to be 7800 gpm. Tentative designs of th… more
Date: December 24, 1959
Item Type: Refine your search to only Report
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Organic Coolant Reclamation Annual Report : December 15, 1958 through December 14, 1959

Description: Potential methods have been examined for the reclamation of high boiler arising from the degradation of polyphenol materials in use as reactor coolants and moderators. To define the chemistry of potential reclamation processes, model polyphenol compounds were used. These include biphenyl, o, m and p-terphenyl, and p-quaterphenyl. Emphasis has been on hydrocracking, redistribution (reaction with benzene), and partial reduction. Preliminary study has been made of the application these techniques … more
Date: December 23, 1959
Creator: Wineman, Robert J.; Adams, J. S.; Gudzinowicz, Benjamin J. & Scola, D. A.
Item Type: Refine your search to only Report
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