TRAIL Microcard Collection - 45 Matching Results

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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chain Reaction of Pure Fissionable Materials in Solution

Description: The critical mass of 94-239 and the corresponding critical dimensions of homogeneous mixtures of 94-239 with various moderating media been calculated as a function of the concentration of 94. A simple transformation makes the figures applicated to92-235. the results are in essential agreement with the preliminary estimated made independently by Oppenheimer and Serber. The problem of the stability of a chain reaction in solution and questions of protection are discussed.
Date: January 1, 1943
Creator: Christy, Robert F., 1916-2012 & Wheeler, John Archibald, 1911-2008
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Contamination of Cooling Water by a P-9 Plant

Description: The following sources of contamination in cooling water of the P-9 plant are considered: (1) Fission recoils, (2) Corrosion of metal, (3) Recoil from aluminum, (4) Induced activity in the water. It is found that for a P-9 plant of 3.5 x 10(4) KW contamination of the river at "X" should not exceed the .1 r criterion unless coating failure occurs. Tables of the amount of coating failure permissible are given as a function of holdup time.
Date: June 1, 1943
Creator: Friedman, Francis L. (Francis Lee), 1918-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Fast Fission on k

Description: The importance of fast neutron fission (i.e., fission caused by neutrons before being slowed down) was recognized by Szilard, and calculations similar to the present one have already been carried out by him, Feld, Ashkin, Wheeler, Wigner and others. The purpose of the present paper is to give a general formula for the contribution of fast fission to the multiplication constant, which will include all the cases already considered and will be applicable to more complicated geometries than those c… more
Date: May 4, 1943
Creator: Castle, H.; Ibser, H.; Sacher, G. & Weinberg, Alvin Martin, 1915-2006
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Temperature on the Resonance Absorption of Neutrons by Uranium

Description: The resonance absorption of uranium for neutrons has been investigated between 20 degree C and 1000 degree C. Experiments were caried out on both UO2, density 4.63, and metal. The resonance activity was measured with respect to that of an iodine monitor at several different temperatures and the ratio of activity at temperature T to that at 20 degree C was determined. The increase in activity is 0.9 per cent per 100 degree C for the oxide and 1.1 percent per 100 degree C for the metal. The perio… more
Date: April 22, 1943
Creator: Mitchell, Allan C. G. (Allan Charles Gray), 1902-; Slotin, Louis; Marshall, John; Nedzel, V. A.; Brown, L. J. & Pruett, John R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effective Temperature of Neutrons in a Lattice

Description: The average energies of neutrons emitted from a graphite column at 22 degrees C were compared by measurement of the cross section of boron for neutrons which are stopped by cadmium. At a distance from the neutron source great enough to insure that the neutrons were in thermal equilibrium the average energies of the emerging neutrons were found to be proportional to the temperature within the limits of the experimental error. A measurement made with boron absorbers which had been thus standardiz… more
Date: February 10, 1943
Creator: Woods, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Leakage of Neutrons from a Heterogeneous Pile

Description: Abstract: "The leakage of neutrons from a heterogenous pile with finite aides is calculated developing the method used in CP-992. The change in the fraction of neutrons absorbed by the moderator is obtained using the results of the calculation of the leakage."
Date: December 27, 1943
Creator: Plass, Gilbert N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low-Density UO2 Pile

Description: The multiplication factor and minimum pile size for a multiplying pile using UO2 powder of density 1 have been computed. It appears that a k of 1.0177 is possible for a volume ration of V/V001=3.33.
Date: February 24, 1943
Creator: Ibser, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement of the Slow Neutron Absorption Cross Section of Some Heavy Isotopes

Description: The following report investigates cross sections for the absorption of slow neutrons of heavy isotopes. The purpose of these measurements was to determine the cross section of an isotope of element 94 for the process of fission by the absorption of a slow neutron, relative to the cross section of U235 for the same process, that is, to measure R.
Date: 1943
Creator: English, Spofford Grady
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Memorandum on Uranium Ore Processing

Description: The following memorandum discusses experiments and methods to recover uranium from Colorado-Utah sandstone and leaving the vanadium in the tails, improving filterability.
Date: November 19, 1943
Creator: Brimm, E. O. & Gailey, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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