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521
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520
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Determination on Neutron Density With Bismuth Foils : Final Report - Problem Assignment 131 - X21P
It is usual to determine the density of neutrons by using foils of metals which become radioactive as a result of bombardment in the region under investigation. From the rate of disintegration of the newly formed radioactive element the number of neutrons absorbed can be calculated. By use of the capture cross section of the element of which the foil is composed the density of the neutrons can then be computed. By counting the alpha particles from a bismuth foil of known weight after exposure to neutrons the density of the neutrons which produced this activity can be calculated. The least accurately known value which enters into this evaluation is the capture cross-section of bismuth for pile neutrons. This value may be improved by future measurements. It is of importance only for absolute measurements of neutron density so that relative values can be measured with considerable accuracy on the basis of known data.
Date:
May 30, 1944
Creator:
Curtiss, Leon Francis, 1895-
Object Type:
Report
System:
The UNT Digital Library
Representation of Slowing Down Functions in Water by Synthetic Kernels
Fermi, Anderson, and Nagle's experimental distribution of Indium resonance neutrons around a point source of fission neutrons in water has been fitted by analytic expressions which are source functions in the two-group, three-group, Fermi and Christy-Wheeler pile theory. The Christy-Wheeler function (exponential followed by a Gaussian) is the best fit; the two-group function (exponential) is slightly better than the Fermi Gaussian.
Date:
June 1, 1944
Creator:
Cahn, Albert, Jr.
Object Type:
Report
System:
The UNT Digital Library
Metallurgical Laboratory, Nuclear Physics Division, Report for the Month Ending May 25, 1944
Technical report with short reports from the (1) Experimental Nuclear Physics Group; (2) Theoretical Physics Group ; (3) Lattice Design Group; (4) Pile Design Group; (5) Exponential Experimental Group; (6) Radiation Group; and (7) Shielding Group.
Date:
June 14, 1944
Creator:
Fermi, Enrico, 1901-1954
Object Type:
Report
System:
The UNT Digital Library
Ames Project, Chemical Research - General Chemistry, Report for the Period of April 10 to May 10, 1944
Technical report. Areas covered are properties of uranium halides, properties of uranium nitrides, and hydride formation at high pressure.
Date:
June 17, 1944
Creator:
Spedding, F. H. (Frank Harold), 1902- & Wilhelm, H. A.
Object Type:
Report
System:
The UNT Digital Library
Comparative Tests of High Voltage Resistors Used for Voltmeter Bleeders
The following report describes tests made for the purpose of determining the accuracy and permanency of various types of high resistance bleeders, and their resistance variation during use over a period of approximately six months.
Date:
June 19, 1944
Creator:
Grauer, Carl T.
Object Type:
Report
System:
The UNT Digital Library
Jacket Temperature Near End of Slug
Some situations which give rise to a hot ring around the slug near the end are considered; namely rounded slug ends in the long cartridge design, and the Wilkins effect in the current unbonded short slug design.
Date:
June 23, 1944
Creator:
Young, Gale Jay
Object Type:
Report
System:
The UNT Digital Library
Modified Liquid Phase Reactor
The following report describes a modified Kraus type reactor that had been constructed for use in bets chemical conversion operations.
Date:
June 23, 1944
Creator:
Zuidema, J. W. & Ballard, A. E.
Object Type:
Report
System:
The UNT Digital Library
The Effect of the Maxwell Distribution of Velocities on the Neutron Density and Diffusion Length in a Metal Sphere
The change in the simple [formula] distribution of neutrons in a spherical lump of uranium caused by the distribution in velocities of thermal neutrons is calculated. If the calculated curve is fitted as well as possible by a simple [formula] curve, it is shown that the value of [formula] obtained in this way is a function of [formula], the radius of the sphere. For small radii the [formula] obtained in this manner will be as much as 25% greater than the [formula] corresponding to average velocity neutrons. The change in the thermal utilization caused by the distribution in velocities is discussed. The flux of neutrons into a sphere is calculated taking into account the velocity distribution and this is compared with the usual theory.
Date:
June 27, 1944
Creator:
Plass, Gilbert N.
Object Type:
Report
System:
The UNT Digital Library
Stability of Split Hollow Cylinders
Abstract: "The behavior of radially split hollow cylinders upon heating is discussed."
Date:
June 29, 1944
Creator:
Karush, William & Monk, A. T.
Object Type:
Report
System:
The UNT Digital Library
Extrusion of Compound Tubes of Aluminum and B4C
Various experimenters have shown (H.H. Gersman U.S. Patent 2,335,590, Nov. 30, 1943; Aluminum Co. of America, various technical papers; also CT-482) that when a billet is extruded by proper technique into a rod (or tube by a floating mandril) that flow of material is streamline and and the extruded article is essentially a space replica of the billet, with linearly distorted coordinates. Advantage is taken of this fact in the manufacture of alclad tubing in which a billet containing an inner core of one alloy with the outer part of another alloy cast around it is extruded together into an integral tube, e.g., to combine high corrosion resistance with high strength. The following experiments were carried out because of the desirability of obtaining a control rod which can be water cooled (or immersed in P9) and which contains boron. For some pile structures it may be desirable to have the major portion of the energy released by the neutron absorption of the control rod be spend in the rod itself by the nuclear reactions [formula] rather than in the surrounding media as is the case when absorption of neutrons is by cadmium according to the reaction [formula]. In the later …
Date:
July 1, 1944
Creator:
Creutz, E. C.
Object Type:
Report
System:
The UNT Digital Library
Test Results on Clinton Alpha Amplifier Used with an Offner Columbia Scaler
Technical report describing development of the Clinton alpha amplifier. The circuit for the Clinton alpha amplifier which is used with an Offner scaler is shown attached to the report. It consists of a pre-amplifier mounted in a cylindrical alpha chamber, followed by a three state amplifier and a pulse height selector in a separate cabinet. Pulses are fed from the pulse height selector in the amplifier to the input tube of the Offner scaler. Through the third stage of the amplifier, this circuit is exactly the same as the California circuit now used by the chemical section for alpha counting. A type 961 Offner scaler was used for these tests. None of the latest Offner scalers type961A, were available to us when the tests were made. Method of testing is given, results are tabulated, computations are made, and eight graphs are given. it appears that the Clinton amplifiers used with a Offner scaler will give substantially the same performance as that given by the California circuit.
Date:
July 1, 1944
Creator:
Ostdahl, H. E.
Object Type:
Report
System:
The UNT Digital Library
Contributions to the Water Problem
Technical report describing the investigation of the short-lived activities produced in oxygen compounds by irradiation with pile neutrons. The most prominent of these activities in cooling water is a beta and gamma emitting activity of about 8 second half-life. Because of its production by epicadmium neutrons it was believed to be the 8 second N16 produced in the pile by n,p on O16. The identification has been accomplished and it is established that the 8 second activity is N16. Part 2 of the report deals with the determination of the recoil range of the Al28 atoms formed by pile n,p reaction on Al27.
Date:
July 3, 1944
Creator:
Novey, Theodore B.
Object Type:
Report
System:
The UNT Digital Library
Progress Report: Development and Construction of Alpha-Counting Equipment
Abstract: An ionization chamber for use in counting alpha particle activity from the air has been devised for counting samples collected with the electrostatic precipitator. The chamber is an adaptation of the breech-locking standard chamber, with a cylindrical high voltage electrode into which the collection foil is placed, and a coaxial rod as a collecting electrode. A geometrical efficiency of close to 50% is obtained.
Date:
July 4, 1944
Creator:
Borkowski, C. J.; Dandl, R. A.; East, J. K. & Firminhac, R. H.
Object Type:
Report
System:
The UNT Digital Library
The Effect of Radiation on the Corrosion of Metals by Water
Technical report. Long-time tests have been made on the effect of various types of radiation on the corrosion of 2S aluminum in simulated W water. In no case was any acceleration of corrosion by the radiation observed; the effect of radiation, if any, appeared to be a protective one. Deuteron irradiation did accelerate the corrosion of mild steel at low flow rates in hot water of pH 6 to 7, but no appreciable effect was observed with copper, stainless steel, or tuballoy. The general theory of the effect of radiation on corrosion is discussed, with the conclusion that no acceleration of corrosion by radiation is to be expected in most cases of practical interest.
Date:
July 6, 1944
Creator:
Allen, A. O. (Augustine O.); Bowman, M. C.; Goldowski, Nathalie; Larson, R. G. & Treiman, L.
Object Type:
Report
System:
The UNT Digital Library
Healing of Fast-Neutron-Induced Changes in Graphite. II. The Effect of Heating During Exposure, Interim Report on Problem 323 MLC 2301
Technical report. The effect of temperature during pile exposure on the fast-neutron-induced change in properties of graphite was studied. Temperatures up to 125 degrees C have no effect upon the rate of increase of elastic modulus; pieces exposed at 300 degrees C on the other hand show no change at all in elastic modulus. The increase in electrical resistance s an inverse function of the temperature of exposure at all temperatures in the range 60 to 300 degrees C.
Date:
July 10, 1944
Creator:
Neubert, Thomas A.; Novick, A.; Schenck, R. & Shapiro, E.
Object Type:
Report
System:
The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending June 30, 1944
Technical report with short reports on (1) P-9 recovery from UO2F2 solution; (2) Correlation of theories on action of radiation on matter; (3) Literature surveys on organic compounds and on chemistry of UO2F2; (4) effect of radiation on organic compounds; and (5) Effect of radiation on 100 area construction materials.
Date:
July 14, 1944
Creator:
Hogness, T. R. (Thorfin Rusten), 1894- & Burton, Milton, 1902-
Object Type:
Report
System:
The UNT Digital Library
Sealing of Holes in Aluminum Sheet by Oxidation
Aluminum oxide occupies a larger volume than the aluminum it contains would fill as metal, consequently, the assumption has been made that holes in metallic aluminum would close by a sufficient amount of oxidation. Therefore, we were asked to investigate the rate of plug formation under conditions to be expected in the pile. For the latter we were requested to approach the pile conditions as nearly as we could by employing the Chicago cyclotron. It seems to us that the problem divides itself into two separate questions: (1) under what conditions may holes be expected to close? (2) if holes do close how much corrosion of uranium may be expected before the closure becomes impervious to water vapor? In this report only the first question is considered. The experiments and theory coupled with the data collected by other workers on the project definitely define the limits within which pores in the aluminum cans may be expected to close by an oxidation process. Under the most favorable conditions only small holes may be sealed in this manner. In the large majority of the cases the holes not only fail to close but become larger.
Date:
July 15, 1944
Creator:
Anderson, S. & Goldowski, N.
Object Type:
Report
System:
The UNT Digital Library
The Behavior of Some Solid Materials Under Pile Operating Conditions
Technical report abstract. The present state of knowledge concerning the effect of pile radiation on a variety of solid materials is reviewed. Radiation corrosion will not be a serious hazard for aluminum or stainless steel but it can be for iron or lead if either are exposed to water. Apart from corrosion the principal uncertainty is in regard to the Wigner effect on the behavior of metals. There is at present no ground for optimism regarding the behavior of tuballoy. The effect on aluminum or a bonding material while less severe must also be considered serious. The expectation in regard to graphite is that its behavior will not cause trouble during the first 100 days of operation although serious troubles will probably arise within two years of operation. Organic materials can be used safely only in regions of limited exposure.
Date:
July 20, 1944
Creator:
Burton, Milton, 1902- & Seitz, Frederick, 1911-2008
Object Type:
Report
System:
The UNT Digital Library
Technical Report for the Months of April, May and June, 1944; Chemical Research - General
Technical report. Quite pure anhydrous ThCl4 in small quantity (8-10 g charge) has been prepared by the action of a mixture of Cl2 and CCl4 vapor on ThO2 at 675 degrees to 725 degrees C.
Date:
July 29, 1944
Creator:
Kraus, Charles A. (Charles August), 1875-1967
Object Type:
Report
System:
The UNT Digital Library
The Distribution of Thermal Neutrons in a Slug with Thick End Caps
The distribution of thermal neutrons in a W slug having a one centimeter aluminum end cap has been calculated on the basis of simple diffusion theory. It is found that the average neutron density, and therefore the power output, at the end of the slug is about 34% higher than the density far from the end cap. This result agrees well with the recent Argonne pile experiments (CP-1729).
Date:
August 3, 1944
Creator:
Wilkins, J. Ernest, Jr., 1923-2011
Object Type:
Report
System:
The UNT Digital Library
Temperature and Heat Flow in a Graphite Electrode
In making various experimental heat studies a power producing metal slug is simulated by a slug with a graphite rod electrode of 3/8" diameter inserted lengthwise through it. There is a helium filled annular space between the graphite and the inner surface of the slug cylinder. Radiant heat passes from the electrode to the metal; with proper adjustment of the electrode current the slug in the steady state will therefor "produce" the same amount of energy from its exterior surface as it would under operating conditions. The question arises, however, as to how uniform the electrode temperature is along its length. And also, in some cases one end of the electrode is embedded in the slug metal; it is then desirable to know how much heat flows by conduction from the electrode into the slug.
Date:
August 3, 1944
Creator:
Schlegel, R.
Object Type:
Report
System:
The UNT Digital Library
Identification and Crystal Structure of Barium Hydrogen Phosphate
From abstract: "The report describes the complete structure of barium hydrogen phosphate, Ba HPO4, as determined by means of x-ray diffraction. The crystal is orthorhombic, with cell dimensions given by a=5.71 A b=7.05 A c=4.61 A. The calculated density is 4.15gm/cm[^]3 for two molecules in the unit cell. The space group is C[subscript]2v[superscript]7-pmn. The barium, phosphorus, and two sets of oxygen lie in the plane of symmetry. The third set of oxygens are in general positions. Parameters for these atoms have been found, and interatomic distances calculated. The positions of the hydrogens are indicated by the characteristics O-H-O distance (2.58A) between two oxygens."
Date:
August 8, 1944
Creator:
Mooney, Rose C. L.; Compton, A. H.; Allison, Samuel King, 1900-1965; Stearns, J. C. & Zachariasen, William H. (William Houlder), 1906-1979
Object Type:
Report
System:
The UNT Digital Library
Neutron Emission by Polonium Oxide Layers
The following report calculates how many neutrons are produced by the O-16([alpha]-n) reaction in a thin and uniform polonium oxide layer.
Date:
August 8, 1944
Creator:
Argo, M. & Teller, E.
Object Type:
Report
System:
The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Analytical, Report for the Month Ending July 1, 1944
Technical report containing short reports on (1) Mass spectrometer studies; (2) Purification of heavy water; and (3) Equilibration studies.
Date:
August 11, 1944
Creator:
Hogness, T. R. (Thorfin Rusten), 1894-; Ashcraft, E. B.; McKinney, D. S. & Voskuyl, R. J.
Object Type:
Report
System:
The UNT Digital Library