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Capture Cross Section of Pb208 for C Neutrons

Description: From abstract: "Using the method of induced radioactivity, the capture cross section of Pb[^]208 for C neutrons is found to be .00045 ± .00015 x 10[^]-24 cm[^]2. This is definitely lower than the value of .001 x 10[^]-24 reported by Maurer and Ramm."
Date: November 5, 1943
Creator: Levinger, Joseph S., 1921-; Compton, A. H.; Allison, Samuel King, 1900-1965; Watson, W. W. & Snell, A. H.
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Chemical Research -- U233 Production and Extraction; Report for the Month Ending June 21, 1943

Description: Abstract. The precipitation of Pa233 with MnO2 from a solution of thorium nitrate has been studied in some detail and seems quite satisfactory up to 36 gm Th(HO3)4 4H2O per 100 cc solution. The concentration of Pa233 with respect to the manganese dioxide carrier and the thorium precipitated with the carrier appears to be accomplished quite well by either a series of MnO2 cycles or thorium iodate cycles. Volatility methods for both the separation of Pa233 from the original thorium and for its … more
Date: June 21, 1943
Creator: Franck, J.
open access

A Colorimetric Method

Description: From abstract: "This paper gives a method for determining Uranium using sodium cresotate as a colorimetric reagent. A precision is obtained of better than 2%. In carrying out analyses for Uranium in corrosion products by existing methods such as ignition to the oxide, silver reductor, or titration with ceric sulfate, it became apparent that a rapid, fairly accurate method for determining uranyl ion would be of great value. Such a method is described in this paper. The most logical color to use … more
Date: June 30, 1943
Creator: Priest, H. F. & Priest, G. I.
open access

The Diffusion Length and the Utilization of Thermal Neutrons in a Heterogeneous Pile

Description: Abstract: "An accurate calculation is given for the quantity which corresponds to the diffusion length in the theory of the pile. The procedure is to establish a relationship between the diffusion length and the change in thermal utilization from a pile with infinite sides to one with sides of a finite length. The calculation of this change in the thermal utilization is then carried through. Approximation to the answer and numerically exact calculations are given in the report. The results show… more
Date: October 6, 1943
Creator: Plass, Gilbert N.
open access

Distribution Coefficient of D₂O Between Triethylamine and Water

Description: Summary: "Water containing 1.8% D2O was distributed between the two liquid phases formed with triethylamine at 20 and 35 C. The triethylamine was removed from each phase by aseotropic distillation with benzene before analyzing the water by determining its density with a quartz float. The ratios of the concentrations of the D2O in the water layer to that in the amino layer were 1.007 and 1.004 at 20 and 35, respectfully. The differences from unity are about the same as the errors of analysis."
Date: August 31, 1943
Creator: Carlson, H. C.
open access

Experimentation on the Extraction of Uranium from Western Ores

Description: The following report supplements a previous report by E.R. Saunders and M. C. Carosella and a report by A. J. Gailey and E. O. Brimm based around the same subject. This report describes a number of tests in which leaching temperatures of 115 and 125 C were tried for the extractions of uranium from western ores.
Date: December 27, 1943
Creator: Saunders, E. R. & Carosella, M. C.
open access

Experimentation on the Extraction of Uranium from Western Ores by Leaching with Sodium Carbonate and Sodium Bicarbonate

Description: Purpose: "The purpose of the following experiments was to obtain data on the selective extraction of uranium over vanadiur from samples of vanadium ores by leaching with sodium carbonate or sodium bicarbonate solutions, with the object of establishing the time, temperature, and concentration conditions necessary for satisfactory extractions."
Date: December 3, 1943
Creator: Saunders, E. R. & Carosella, M. C.
open access

Memorandum Listing the Areas in Colorado, Utah, Arizona and New Mexico that are Geologically Favorable for Developing Large Reserves of Vanadium Ore by Prospecting

Description: Introduction: Vanadium ore is being mined at many places in western Colorado, southeastern Utah, northeastern Arizona, and northwestern New Mexico (fig. 1). Eight mills in this region produced about 4,300,000 pounds of V2 05 in 1942, representing about 90 percent of the vanadium obtained from domestic sources. Although ore production has mostly exceeded mill capacity since 1937, production during the last half of 1942 averaged only about 19,000 tons or ore a month, whereas the capacity of these… more
Date: April 10, 1943
Creator: Fischer, R. P.
open access

Metallurgical Laboratory, Chemical Research - Analytical, Graphite Purity Research Program

Description: Abstract. Chemical analytical studies of graphite raw materials have revealed new sources of petroleum cokes and pitches of greater purity than those previously used in the manufacture of project graphite. The use of these raw materials of exceptional purity has resulted in an improvement in k of the order of one per cent as compared with the AGOT-AGNT graphite typical of the previous production. A study of the graphitizing process has shown that no dangerous impurities are introduced in the… more
Date: December 22, 1943
Creator: Boyd, G. E.; Curtis, R. E. & Johnston, W. H.
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Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943

Description: Technical report that information has bee obtained on the effect of beta and gamma radiation on the electrical resistance of insulating materials The results are summarized. The recovery to original resistance values has been measured. In general, the initial rate is rapid for the first few hours; the rate then decreases sharply. Certain samples show evidence of complete recovery. Effects on mechanical properties of several plastics has also been studied. Data on gas evolution from severa… more
Date: May 15, 1943
Creator: Franck, J.
open access

Optimum Design of Catalytic Towers

Description: Abstract: "This paper gives an arithmetic method of computing the number of sections required in a catalytic tower to produce a given enrichment. It also tells how to calculate the enrichment of a tower with a given number of sections. The problem of the most economical design of catalytic towers is solved. Methods are given for determining the temperature, the efficiencies of catalyst beds and strippers, the relative production rate, and the water vapor-hydrogen gas ratio which give the optimu… more
Date: March 13, 1943
Creator: Mayer, Harris
open access

Physical Properties of Uranyl Sulfate Solutions

Description: Abstract: Measurements are reported of the solubility of uranyl sulfate in water at several temperatures, of the density of uranyl sulfate solutions as a function of concentration, of the variation of density of uranyl sulfate solutions of three different concentrations over a temperature range from 0[degree]C. to about 93[degree]C., and of the pH of uranyl sulfate solutions as a function of concentration as well as of temperature. The pH measurements were taken on uranyl sulfate samples prepar… more
Date: December 15, 1943
Creator: Helmholz, Lindsay. & Friedlander, G.
open access

Polarographic Determination of Uranium in Dust Samples

Description: Abstract: "Samples of dust are collected from the atmosphere with a Mine Safety Appliance Co. electrostatic precipitator and analyzed for uranium by means of a dropping mercury electrode apparatus. Two to three micrograms of uranium can be detected in a cell solution volume of 1 ml. Iron, nickel and chromium present in shop dusts do not interfere. Copper may interfere if present in excess but may be removed by a sulfide precipitation. Directions for preparation of cell solution and operation of… more
Date: August 30, 1943
Creator: Smith, Stanton B.
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