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Determination of the 14-Mev Li7 (n,n'a)T Cross Section from Sphere Multiplication and Transmission Measurements
By utilizing lithium spherical shell transmission and multiplication measurements, the Li7(n,n'y)Li7 and the He6-production cross sections, it is possible to deduce that the 14-Mev Li (n,n'a)T cross section is 325 ± 75 mb. A spectrum for neutrons degraded in energy between 0 and 12 Mev is also given.
Date:
July 1054
Creator:
Thomas, R. G.
Object Type:
Report
System:
The UNT Digital Library
Patent of Invention--Gr 5--Cl.3--Bearing
The object of this invention is a bearing: a thrust bearing. This bearing is one in which the bearing faces is a continuous annular surface and the other an annular surface divided into shoes having the form of sectors.
Date:
October 28, 1925
Creator:
Fulpius, Edward
Object Type:
Report
System:
The UNT Digital Library
Applied Potential Corrosion of Aluminum and 18-8 Stainless Steel Alloys
Introduction: In anticipation of the design of equipment for heat transfer tests, a series of short exposure corrosion tests was initiated in an effort to determine the order of magnitude of the corrosion involved. Information was required on the effect on corrosion rates of applying a potential between two concentric tubes, the annulus between them containing condensate water.
Date:
March 13, 1930
Creator:
Sanborn, Kenneth L.
Object Type:
Report
System:
The UNT Digital Library
Selected Russian Papers on Geochemical Prospecting for Ores
A selection of Russian papers on the geochemical prospecting for ores
Date:
1939/1946
Creator:
Sokoloff, V. P.; Hawkes, H. E. (Herbert Edwin), 1912-1996; Ratsbaum, E. A.; Sergeev, Evgeniĭ (Evgeniĭ Aleksandrovich); Sergeev, Evgeniĭ (Evgeniĭ Aleksandrovich); Sergeev, Evgeniĭ (Evgeniĭ Aleksandrovich) et al.
Object Type:
Report
System:
The UNT Digital Library
The Conversion of UF4 to U3Os
Methods of conversion of UF4 to U3O8 by fusion with ammonium oxalate dihydrate and other salts are described.
Date:
May 28, 1941
Creator:
Tevebaugh, A. D.; Tevebaugh, R. D.; Cline, W. D. & Warf, James C.
Object Type:
Report
System:
The UNT Digital Library
The Use of Sodium Diethyl Dithiocarbamate as a Reagent for the Determination of T
This report investigates the use of sodium diethyl dithiocarbonate as a reagent for the determination of T.
Date:
1942
Creator:
Jones, A. G.
Object Type:
Report
System:
The UNT Digital Library
Interaction of Be with Fission Neutrons
To determine whether or not the (n,2n) reaction in Be would produce a net increase in fission neutrons in a power plant, the distribution of In resonance neutrons slowed down from fission energies in a graphite block was measured with and without a 2" of Be in front of a U3O8 slab undergoing fission. The thermal neutrons producing the fissions were obtained by slowing down neutrons from a cyclotron source. The observed distribution without Be was well represented by a Gaussian source range 36 cm. (corresponding to an initial fission energy of 3 MeV) and a similar sink of range 7.8 cm. The total In resonance intensity with Be was 5% less than without Be. On the assumption that the effect of the Be is entirely due to its different mean free path and moderating power, the In distribution with Be was calculated. Since the m.f.p. as a function of energy is not known for Be, two separate calculations were made using the highest (2.9 cm.) and the lowest (1.80 cm.) possible values for the effective Be m.f.p. Both calculated curves were found to be higher than the observed Be distribution, indicating that at least 10% of the fission neutrons …
Date:
April 29, 1942
Creator:
Borst, L.; Allison, S. K.; Wheeler, John Archibald, 1911-2008 & Weinberg, Alvin Martin, 1915-2006
Object Type:
Report
System:
The UNT Digital Library
An Attempted Separation of Mercury Isotopes
The following document describes the analysis on an attempt at separating mercury isotopes by making their environments as widely different as possible.
Date:
April 30, 1942
Creator:
Kauzmann, Walter, 1916-
Object Type:
Report
System:
The UNT Digital Library
Capture Cross Section of Si for Thermal Neutrons
The following report analyzes different values and measurements that give the same results for the captured cross section of thermal neutrons for Si.
Date:
May 6, 1942
Creator:
Coon, J. H.
Object Type:
Report
System:
The UNT Digital Library
Examples for Pressure Drop Calculations in Parallel Flow Helium Cooling
Pressure drop calculations are shown for He cooled power plants ranging from 400,000 kw to 30,000 kw.
Date:
June 18, 1942
Creator:
Feld, Bernard T. (Bernard Taub), 1919-1993 & Szilard, Leo
Object Type:
Report
System:
The UNT Digital Library
The Extraction Method of Purification of Uranyl Nitrate
Technical report. Three extractions of a diethyl ether solution of uranyl nitrate with small portions of water are effective in removing rare earths, as is shown by radio-gadolinium and radio-europium tracer experiments. A study of representative ethers, alcohols, ketones, and esters showed that diethyl ether and a mixture of 85% ethyl methyl ketone with 15% xylene are the best solvents for the extraction.
Date:
August 28, 1942
Creator:
Myers, L. S., Jr.; Anderson, K. C.; Wexler, Sol & Boyd, G. E.
Object Type:
Report
System:
The UNT Digital Library
On Certain Phase Equilibria in the Ternary System Uranyl Nitrate--Ether--Water at 25° and at 1°C
This report follows a study that deals with a portion of the ternary diagram previously analyzed, namely the boundary curves which separate the central area of two coexistent liquid phases from the two border stripe representing one-phase liquid systems.
Date:
October 22, 1942
Creator:
Van Name, Ralph Gibbs
Object Type:
Report
System:
The UNT Digital Library
Effect of Temperature on the Surface of Cast Uranium Metal
Technical report. Photomicrographs showing the effect of heating polished uranium surface at 600, 700, 850, and 1000 degrees C, and sandblasted and cut surface at 1000 degrees C are included.
Date:
December 3, 1942
Creator:
Johns, I. B; Newton, A. S. & Gladrow, E. M.
Object Type:
Report
System:
The UNT Digital Library
Poisoning and Production in a Power Plant
The yield of 49, the efficiency of production of 49, and poisoning in a power plant are discussed. Only the crudest of estimates of the poisoning are possible: these indicated that production will probably not be hampered by poisoning. In this case the yield of 49 could be as high as 3 kg/ton but only about 2 kg/ton is compatible with a fairly high efficiency. In the case that production is stopped by poisoning, smaller yields, proportional to the tolerable loss in k, are obtained. In this case the yield will be improved by a factor of 2 or 3 if only the most poisoned parts are extracted and replaced by new uranium.
Date:
December 15, 1942
Creator:
Ashkin, J.; Christy, Robert F., 1916-2012 & Feld, Bernard T. (Bernard Taub), 1919-1993
Object Type:
Report
System:
The UNT Digital Library
Chain Reaction of Pure Fissionable Materials in Solution
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
Object Type:
Report
System:
The UNT Digital Library
Measurement of the Slow Neutron Absorption Cross Section of Some Heavy Isotopes
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
Object Type:
Report
System:
The UNT Digital Library
The Toxicity of Fluorine
The following report discusses the toxicity of fluorine as described in literature on fluorine intoxication and case studies of Roholm's experimental observations.
Date:
1943
Creator:
Ferry, J. L.
Object Type:
Report
System:
The UNT Digital Library
The Vapor Phase Hydrolysis of the Trichlorides of Lanthanum, Praseodymium, Samarium, and Americium
The following report studies the reactions of vapor phase hydrolysis of the trichlorides of lanthanum, praseodymium, samarium, and americium with gas mixtures of HCl and H2O passing over the solid materials mounted on a cantilever-type quartz fiber microbalance. This report calculates the values of the heats and entropies of the reactions, as well as the heat formation of LaCl3, 1254.9 kcal mol-(-1) that was obtained by determining the heat of the solution of La metal in 1.5M HCl.
Date:
1943
Creator:
Broido, Abraham
Object Type:
Report
System:
The UNT Digital Library
Preliminary Report on High Concentration Deuterium by Catalytic Exchange Reactions
From abstract: "This report contains the theoretical analysis of a plant to concentrate deuterium from 2 atoms% to 90 atoms% by the NH3-H2 exchange reaction."
Date:
February 4, 1943
Creator:
Mayer, Harris & Bonner, Robert
Object Type:
Report
System:
The UNT Digital Library
Effective Temperature of Neutrons in a Lattice
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 standardized in the graphite column indicated neutrons emerging from the chain reacting pile to have an average temperature approximate 60 +- 50 degrees above that of thermal neutrons emerging from the graphite column at 22 degrees C. Such a measurement made inside the chain reacting pile indicated the average temperature of neutrons therein to be about 65 degrees +- 15 degrees above the average temperature of neutrons in the graphite column.
Date:
February 10, 1943
Creator:
Woods, L.
Object Type:
Report
System:
The UNT Digital Library
Temperature Coefficient of the Reproduction Factor for Different Lattice Arrangements
The temperature coefficient is calculated for various lattice arrangements, taking into account the variation of [formula], suggested by Fermi. Four contributions are included: leakage, levelling of the dip in thermal neutron density in the lump, resonance absorption, and hardening of the neutrons as they penetrate a metal lump. The departure of neutron temperature from lattice temperature decreases the total coefficient. Values are given for 3 typical piles; in general, the larger the uranium elements, the less stable the pile. A rod lattice tends to be more stable. A pile with metal lumps over 50 lbs. will be unstable.
Date:
February 10, 1943
Creator:
Morrison, P.
Object Type:
Report
System:
The UNT Digital Library
Low-Density UO2 Pile
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.
Object Type:
Report
System:
The UNT Digital Library
Radioactivity of the Cooling Water
The most important source of radioactivity at the exit manifold of the pile will be due to O19, formed by neutron absorption of O18. A recent measurement of Fermi and Weil permits to estimate that it will be safe to stay about 80 minutes daily close to the exit manifolds without any shield. Estimates are given for the radioactivities from other sources -- both in the neighborhood and farther away from the pile.
Date:
March 1, 1943
Creator:
Wigner, Eugene Paul, 1902-1995.
Object Type:
Report
System:
The UNT Digital Library
Optimum Design of Catalytic Towers
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 optimum combination of operating pressure, cross sectional area, number of sections, and volume of catalyst in the tower. Simple directions as to how to make the calculations are included."
Date:
March 13, 1943
Creator:
Mayer, Harris
Object Type:
Report
System:
The UNT Digital Library