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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.
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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-
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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SER Temperature Coefficient

Description: Experimentally determine the overall isothermal temperature coefficient of the SER up to the design operating temperatures.
Date: December 31, 1959
Creator: Johnson, J. L.
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report, August 1959. Chemical Technology Division

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed, two Druhm runs were terminated due to malfunction, calculations of particle temperature were performed, materials handling flowsheets were completed, and a literature survey is being conducted.
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E. (Marvin E.), 1926-
Partner: UNT Libraries Government Documents Department
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14-Year 113Cd

Description: The half lives of Cd/sup 113m/ and Cd/sup 115m/ have been redetermined to be 14 sintering time 2 years and 44.2 sintering time 0.5 days, respectively. The ratio of Cd/sup 113m/Cd/sup 115m/ yields from thermal-neutron fission of U/sup 235/ is 0.27 sintering time 0.03, and the ratio of (n, ) formation cross sections is 0.31 sintering time 0.03. Combination of these ratios with literature values for the Cd/sup 115m/ fission yield and (n, ) formation cross section gives (1.9 sintering time 0.2) x 1… more
Date: October 31, 1959
Creator: Wahl, Arthur C.
Partner: UNT Libraries Government Documents Department
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APPLIED HEALTH PHYSICS SEMI-ANNUAL REPORT FOR JULY 1956-DECEMBER 1956

Description: Routine monitoring procedures are summarized. Based on samples collected by continuous air monitors, the wcekly average value for air contamiration in the laboratory area was 1.98 x 10/sup -12/ mu c/cc. Radioactive fall-out was determined by measuring the total activity and total number of particles collected on gum paper fall-out trays. Two peak periods of activity in July and September were concluded to be the result of weapons tests. Meteorological data are tabulated. Data are included from … more
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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Calculation of the G Factor for Gas Scattering Experiments

Description: The "G factor'' relating the yield to the beam intensity, target density, and scattering cross section is calculated for several types of aperture boundaries. The case of a front aperture composed of two parallel edges of infinite height with a rear aperture of any shape is calculated up to terms in the fourth derivative of the cross section. (W.D.M.)
Date: October 31, 1959
Creator: Silverstein, Edward A.
Partner: UNT Libraries Government Documents Department
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Department of Chemical Engineering Progress Report for September 1, 1957 Through June 30, 1958. Part I. Thermal Conductivity of Deuterium Oxide

Description: The thermal conductivity of heavy water was found to vary from 0.345 at 105 deg F through a maximum of 0.375 at about 265 deg F to 0.371 at 339 deg F. The conductivity was determined by a steady-state method in a cylindrical apparatus having an over-all length of 11.35 inches and a liquid layer about 0.061 inch thick. A temperature drop of approximately one degree Fahrenheit across the liquid was maintained. The temperature drop was measured with thermistors. The apparatus was calibrated with l… more
Date: October 31, 1959
Creator: Baker, B. L.
Partner: UNT Libraries Government Documents Department
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Diffusion of Uranium with Various Transitional Metals; DIFFUSION DE L'URANIUM AVEC QUELQUES METAUX DE TRANSITION

Description: The diffusion process in uranium and its alloys was studied from 550 to 1075 deg C with diffusion couples of U with Zr, Mo, Ti, and Nb and with the alloys U--Nb and U--Mo. A brief description is given of the experimental methods. Results relative to the concentration-penetration curves are presented, and the coefficients of diffusion are calculated. The equilibrium diagram was established for the U--Zr system. The results obtained by micrographic examination, microhardness measurements, and aut… more
Date: October 31, 1959
Creator: Adda, Y. & Philibert, J.
Partner: UNT Libraries Government Documents Department
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ELK RIVER REACTOR. Quarterly Project Report for December 1958 January- February 1959

Description: Design and construction are proceeding satisfactorily. Fuel capsule irradiation studies are progressing, and preparation of specifications for fuel elements and assemblies is almost complete. Other design, development, and construction progress is reported. Instrumentation developments are described. Reactor physics studies are reported. (For preceding period see AECU-4013.) (T.R.H.)
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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ELK RIVER REACTOR. Quarterly Project Report for March-April-May 1959

Description: An alternate design of the Elk River Reactor was completed during the quarter. Three points were emphasized in the study: performance capability to provide 116 Mw(th) output; fuel costs of the reference design versus alternate fuel media and cladding; and reactor control modifications to provide sufficient reactivlty to eliminate soluble hold down'' poisons, permit higher power operation and obtain a greater fuel life. Work is summarized on fuel element and material development progra… more
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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Elk River Reactor Quarterly Project Report for September-October-November 1958

Description: Design and construction are proceeding on schedule. Physics and shielding calculation results are reported and discussed. Studies of the high- pressure B injection safety system are described. The programs for fuel element and materials development, reactor vessel and internal components, process and superheater, reactor building and plant facilities, and instrumentation are outlined. (For preceding period see AECU-3991.) (T.R.H.)
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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AN EVALUATION OF MERCURY COOLED BREEDER REACTORS

Description: Under the New Reactor Concepts Evaluation Program sponsored by the United States Atomic Energy Commission. Advanced Technology Laboratories (a Division of American Radiator & Standard Sanitary Corporation) has undertaken am investigation of the technical feasibility and economic potential of the use of boiling mercury as a coolant for fast breeder reactors The investigation was performed between January 1, 1959, and October 31. 1959. This is the final report on that investigation and is submitt… more
Date: October 31, 1959
Creator: Bradfute, John O.; Battles, Donald W.; Clark, George S.; Corridan, Robert E.; Gellenbeck, Edward T.; Kavanagh, Devereux L. et al.
Partner: UNT Libraries Government Documents Department
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Fuel Elements Conference Held at Gatlinburg, Tennessee, May 14-16, 1958

Description: The fuel element conference provided a favorable medium for presentation and discussion of recent developments in the field of solid fuel elements. The conference was designed to replace the more general Metallurgy Information Meetings held annually in the past. The scope of the meeting embraced the design fabrication, performance, and material problems of fuel elements. (W.D.M)
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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HIGH TEMPERATURE PROPERTIES OF URANIUM AND ITS ALLOYS

Description: Data are presented on the mechanical and physical properties of high- purity and normal uranium and for a range of dilute uranium alloys at temperatures up to 700 deg C. The results of thermal conductivity and thermal expansion determinations for a range of alloys are discussed, and some results on the latent heat of fusion and volume change on melting are presented. Results of dilute alloy creep tests are reported and correlated with thermal cycling data and resistence to swelling under irradi… more
Date: October 31, 1959
Creator: McIntosh, A.B. & Heal, T.J.
Partner: UNT Libraries Government Documents Department
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INFORMATION MEETING ON GAS-COOLED POWER REACTORS, OAK RIDGE NATIONAL LABORATORY, OCTOBER 21-22, 1958

Description: This meeting is one of a series of Civilian Power Reactor Conferences and was held colncident with an AEC invitation to industry to bid on the construction of a gas-cooled facility. Papers are presented on design studles, hazards, components, costs, materials, and design concepts for specific reactors. (W.D.M.)
Date: October 31, 1959
Partner: UNT Libraries Government Documents Department
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IRRADIATION BEHAVIOR OF ThO$sub 2$-UO$sub 2$ FUELS

Description: ThO/sub 2/-UO/sub 2/ fuels have been studied because of certain advantages possessed by this type of fuel over UO/sub 2/. Pellets of ThO/sub 2/- UO/sub 2/ have been found to be highly stable dimensionally under irradiation. Various experimental assemblies which have been irradiated have included Al, Zircaloy, and stainless steel cladding, with the annulus surrounding the pellet filled with air, He, NaK, or Pb. A full-scale core of pellets lead-bonded to Al tube-plates has been used successfully… more
Date: October 31, 1959
Creator: Kittel, J.H.
Partner: UNT Libraries Government Documents Department
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Mechanisms of Surface Adsorption in Homogeneous Reactor Loops. Semi- Annual Report No. 2 for 1 July to 31 December, 1957

Description: Homogeneous reactor operating conditions in which solids and deposits are formed on loops were examined. Methods of removing existing deposits are also considered. Experiments were conducted to study the characteristics of solids and deposits on type-347 stainless steel and on Zircaloy-2 specimens using simulated homogeneous reactor solutions in a rocking autoclave. Ferric and chromic sulfate were added to the solution in some of the tests to form solids by hydrolysis. Four tests were run at 30… more
Date: October 31, 1959
Creator: Eding, H. J.
Partner: UNT Libraries Government Documents Department
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