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Metallurgical Laboratory, Physics Section, Report for the Month Ending May 31, 1945
Technical report with short reports from the (1) Physics Section I; (2) Physics Section II ; and (3) Physics Section III.
A Case of Rod Warping
Warping of a rod by a variation in heat transfer coefficient around the periphery is considered. Estimates for some simple cases are given, and a more precise numerical calculation is carried out in ne instance.
Thermal Stresses Arising from Defective Strip in Bond
Stresses set up by an insulating strip in the bond are estimated and found to be small compared to those normally present without the defect.
The Diffusion Length of Thermal Neutrons in Uranium
Measurements made in a uranium cylinder result in a mean value of 1.55 cm. for the diffusion length L for distances of 1 to 4 cm. from the base of the cylinder. Calculations give a value which agrees with the experimental result and show further that L increases from 1.40 to 1.63 cm. as the neutrons diffuse a distance of 5 cm. into the uranium.
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.
The Effect of Fast Fission on k
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 considered by the previous writers.
On the Multiplication Constant of Homogeneous Mixtures of U with Various Moderators
The following represents a summary of calculations on the multiplication constant of homogeneous mixtures of uranium and different moderators. These calculations were made possible by Fermi's determination of the age of neutrons and by the extrapolation to higher scattering cross-sections of the resonance absorption of uranium as measured by C. Creutz. According to Fermi, the former quantity is 120 sq. cm. The latter is given in the two attached graphs. The first (Fig.1) of these goes as high as a scattering cross-section of 70 x 10-24 cm.2 per uranium atom, and its highest point is taken from a measurement of Cruetz's in which a mixture of U3O8 and graphite was used.
The Preparation of High-Purity Beryllium Oxide
Abstract. A method for the preparation of beryllium oxide of high purity is presented. Beryllium basic acetate (BeO-3Be(C2H3O2)2) is prepared from the metal or a convenient salt, a chloroform solution of this material extracted with redistilled water, the dried basic acetate distilled in a quartz apparatus, and this purified material converted to the oxide by fuming down with sulfuric acid and igniting at 1000 degrees C. Impurities detectable spectrographically were reduced to a very low level.
The Extraction of Uranium into Hexone as Uranyl Thiocyanate from Thorium Nitrate Solutions
Technical report with six sections describing the process: (1) The reaction of HN)3 with HSCN; (2) The distribution of nitric acid between hexone and water; (3) The distribution of HSCN between hexone and water; (4) The solubility of thorium sulfate in various extraction solutions; (5) The distribution of protoactinium and fission elements between hexone and aqueous thiocyanate solutions; and (6) Separation of uranium from thorium by extraction into hexone as UO2(SCH)a.
Analysis of Heavy Water by Equilibration
Technical report discussing that the deuterium concentration of heavy water can be determined by equilibrating the water with deuterium gas in the presence of a catalyst with subsequent analysis of the equilibrated gas on the mas spectrometer. The apparatus for equilibration analyses maybe be considered in three parts: 1) apparatus for introducing the ingredients into the reaction chambers; 2) the reaction chambers; 3) the mass spectrometer for analysis of the equilibrated gas. The isotopic composition of the deuterium gas to be used as the starting material is primarily governed by what gases are available. In general it is best to use gas within about one percent on either side of the final equilibrium composition. No reaction takes place between deuterium gas and water molecules in the absence of a catalyst. Platinum oxide is used as the catalyst.
Analysis for Oxide in Thorium Metal
Abstract. to estimate the oxygen picked up by thorium in casting a rapid method of running the acid insoluble content was developed. the quickest procedure consists of reacting with mixed acids, fuming with perchloric and filtration to separate the "free" thorium from the "combined". The precipitate is ignited and weighed as thorium dioxide.
Preparation of U233
Technical report. The object of the research is to determine the procedure and equipment for the preparation of U233 on a semi-works scale. The general proposed procedure is that thorium carbonate in aluminum cans will be irradiated with pile neutrons. The Pa233 resulting from neutron absorption the Th232 and the decay of Th233 will be extraction from 99% of the thorium and the natural U in thorium by MnO2 precipitations. The Pa233 will then be allowed to decay to U233 which in turn will be isolated from the remaining Th and partially decayed Pa233 by ether extraction.
Metallurgical Laboratory, Chemical Research - Heavy Water, Report for the Month Ending May 1, 1944
Technical report with short reports on (1) Heavy water analysis and standardization, and Specific gravity of pure D2O; (2) Homogenous exponential experiment; (3) Recombination of pile gases; (4) Slurry pumping studies; and (5) Electron microscope laboratory.
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943
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 several organic materials including those suggested by the physiological shield have been extended to include both beta and deuteron bombardments. Samples of "Press-wood" are being evaluated. The effect of current on the H2O2 production in water containing I- has been studied at several I- concentrations. Water contain-dissolved CO2 shows the presence of oxidant (presumably H2O2). H2O2 has been produced by recoil protons from the scattering of fast neutrons in de-oxygenated water. Radioactive solutions do not greatly affect the applicability the glass electrode providing the electrode is thoroughly washed with distilled water before immersion in the standard buffer solution.
The Conversion of UF4 to U3Os
Methods of conversion of UF4 to U3O8 by fusion with ammonium oxalate dihydrate and other salts are described.
Summary of the Research Progress Meeting
Technical report includes three reports of research progress: 1)Neutron scattering by A. Bratenahl; 2) Nuclear Cross Sections, Norman Knable.
Summary of the Research Progress Meeting
Technical report includes three reports of research progress: 1)Meson Mass Determination by Grain Counting, W. H. Barkas; 2) The Magnetic Beta Ray Lens Spectrograph, A. C. Helmholz; 3) Anthracene Counters, E. Martinelli.
The Toxicity and Metabolism of Plutonium in Laboratory Animals
Introduction. The main objective of the Metallurgical Project was the preparation of large quantities of plutonium 239, an isotope of element 94, by the interaction of neutrons and uranium. At the beginning, only predictions of its chemical and biological properties could be made since it is a new element. It was predicted that it would be toxic to tissue by virtue of its high atomic weight, and in addition, that it would be toxic by virtue of its radioactivity. Thus, the preparation and use of the element on a large scale meant the manipulation of, and possible exposure to, toxic quantities. It was, therefore, of practical importance to obtain data which would elaborate on the predicted toxicity. The objectives of the work reported here were to establish the acute toxicity of plutonium in experimental animals and to study the distribution of the element in the body after the administration of a wide range of doses. In the interest of economy of what was, at that time, a rare substance, and of animals and facilities, these two objectives were frequently pursued in the same experiment. The information obtained from the separate experiments is therefore frequently incomplete in one or another respect. An attempt has been made to present the data obtained in a number of experiments as a unit serving the above objectives. Most of the studies were made with the plus 6 valance state because of its intrinsic value and because it is easier to handle at relatively high pH. it is probably quickly converted to a lower valance state by the body fluids. Because of the importance of this new element and because of the number of problems which had to be investigated, concurrently, other groups in the project have studied phases of these and related problems.
Use of Redux Adhesives for Bonding Metal
Redux is a thermosetting synthetic resin manufactured by the Resinous Products & Chemical Co., Washington Square, Philadelphia 5, Pa. According to the manufacturer, it is intended for bonding metal to metal and metal to wood. It was apparently intended to replace rivets in aircraft structural parts and recent information indicates that a British airplane, the DeHaviland Dove, is in production using this resin. The adhesive was originally developed in England by Aero research Ltd. Experience at this laboratory has been confined to use of the resin for bonding electrical grade silicon steel laminations. Very strong bonds have been obtained under properly controlled conditions. The bond strength is sufficient to tear 29 gauge (.014") steel when attempting to peel off individual laminations. The bond is sufficiently homogeneous to prevent leaks parallel to the plane of the laminations into a high vacuum system. Experiments at the laboratory have been designed to test the adhesive for use in bonding the laminations which form the pole tips and vacuum chamber lids for the synchrontron magnet.
Electrolytic Reduction of Uranyl Ion
From introduction: "Due to the hydrogen overvoltage at the surface of a mercury cathode, uranium solutions is hydrochloric acid may be reduced not only to the tetravalent state, but until considerable trivalent uranium is formed. Other metallic ions act as oxidation-reduction catalysts as well as being reduced themselves. The following paper is a study of the various reactions taking place in solution and at the surface of the cathode."
The Beta-Gamma Hand and Foot Counters
Abstract: This is basically a counting rate meter, with an alarm circuit, operating from four GM tubes as the detecting elements. The Hand Counter comprises four logarithmic counting rate meters working from four GM tubes mounted individually, with associated electronic circuits, in suitable shields with a metal mesh type of window. Both sides of both hands are sampled simultaneously. In the Foot Counter, two GM tubes are separately and mounted in a suitable mesh window shielded with the electronic circuit; the foot counter uses only two counting rate meters, and both feet are sampled simultaneously. Each circuit is built in two parts; two tubes are in the shield and the balance of the circuit is in the electronic unit which is a standard 17" x 13" chassis. Circuit diagrams are included.
Events of importance for week ending May 18, 1949
This report details events of importance reported by the Hanford Operations Office for the week ending May 18, 1949.
Events of importance for week ending May 4, 1949
This report details events of importance reported by the Hanford Operations Office for the week ending May 4, 1949.
[Office of Hanford Directed Operations events of importance for week ending May 25, 1949]
This report details events of importance reported by the Hanford Operations Office for the week ending May 25, 1949.
[Office of Hanford Directed Operations events of importance for week ending May 11, 1949]
This report details events of importance reported by the Hanford Operations Office for the week ending May 11, 1949.
INVESTIGATION RELATING TO THE CHEMISTRY OF URANIUM
No Description Available.
Analysis of Columbia River mud
This report is a copy of a letter sent on May 23, 1944, concerning the analytical evaluation of Columbia River water by Clinton Laboratories.
Sampling of Effluent and River Water
This document contains information about the sampling program at Columbia River during May 5, 1944. Topics discussed include: securing representative samples; analysis of the samples looking at temperature, bacteriological content, dissolved oxygen, and physical tests; and the method and equipment used in the sampling procedure.
Events of importance for week ending May 26, 1948
Operation of the 100F pile is reported on. Ongoing construction is described; detailing population and occupancy. Visitors and the Schenectady report are discussed. A copy of the June 4 letter from Carleton Shugg to Carrol L. Wilson pertaining to flooding of the Columbia and Yakima rivers is included.
Tubular aluminum dummy slugs
No Description Available.
Transmittal Letter Regarding Eleven Graphs Showing the Quantity of Dissolved Oxygen in the Columbia and Yakima Rivers
This document contains information concerning the dissolved oxygen content of the Columbia River and Yakima Rivers near the Hanford Production Reactors on May 3, 1946. Data is presented in graphed form with weekly variations plotted.
Turbidity coagulant for Columbia River water
In this document, information about the need for a better compound to for filtering process water from the production reactors. It was found that the natural turbidity in the Columbia River was high enough to necessitate the use of a coagulant to minimize the passage of iron through filters. Tests indicated that Ferrisul was the better of the two compounds tested.
100 Areas Technical Activities Report - Engineering, April 1947
This is the first of a series of monthly reports covering details of the work of the Engineering Group of the Pile Technology Section of the Technical Department. The monthly Slug Inspection Report is being discontinued as a separate document and is being incorporated in this group report. Included is work on corrosion and blistering; graphite expansion; and irradiation studies.
Temperature moments vs poison moments
The excess reactivity available in an operating pile is absorbed in poison columns and horizontal rods. The temperature distribution of the pile is determined by the relative strengths and locations of the poison columns and the configuration of control rods used. A method for adjusting poison columns and rods to improve upon the pile`s temperature distribution is given in Document {number_sign}7-2654, ``Procedure for Improving Temperature Distribution via Rods and Columns,`` Wheeler and Menegus to Jordan, September 9, 1945. A relationship between poison moment (inhour lattice units) and temperature moments (per coat) was theoretically derived in the above document and has since been measured on several occasions on the basis of operating experience. A survey of recent operating data for the F Pile has been made by H. A. Gauper, Jr. with the intent of improving the method for obtaining the temperature and poison moments and relating changes in the two. This study was concerned with only the horizontal and vertical dipole moments. The results of Mr. Gauper`s investigation are summarized in this memorandum.
[Technical progress report for Hanford 100 and 300 areas]. Progress report ending May 15, 1943
This weekly report details technical activities for the week ending May 15, 1943.
100 Areas technical activities report: Physics, April 1947
This monthly report details Physics Department 100 Area technical activities for the month of April 1947.
Reduction of size of water passages by thermal expansion: W pile
No Description Available.
Reference your telephone call of May 5, 1944 to Mr. Boiler
This document provides the analytical reports on the aluminum-silicon alloy, tin and copper analytical reports are also provided.
Technical Division weekly progress report for period ending May 22, 1943
This report details Technical Division activities for the week ending May 22, 1943.
River water temperature survey
Data acquired from the temperature survey of the Columbia River, April 2, 1945, is presented.
100 Areas: (For technical progress letter No. 98), May 14--May 20
This technical progress report details 100 Area activities for the time period of May 14 through May 20, 1946.
Health problems associated with investigation of off-plant uranium rolling. Rough draft
The following is a report of a trip to the Simonds Saw & Steel Company, Lockport, New York, on May 3, 1949. The purpose of the visit was to observe the various operations involved in the rolling of uranium rods at this plant and health problems associated with the rolling operations.
100 Areas: (For technical progress letter No. 99), May 21--May 27
This report details 100 Area reactor operation for the time period of May 21 through May 27, 1946.
100 Areas: (For technical progress letter No. 95), April 23--29
Reported are: physics (B Pile, D Pile, F Pile, general physics); and water, corrosion and engineering (process water control and pressure drop studies, corrosion, graphite expansion).
100 Areas: (For Technical Progress Letter No. 96), April 30--May 6
No Description Available.
100 Areas: (For Technical Progress Letter No. 97), May 7--13
Physics information for the D and F piles is presented. Thermal conductivity, reactivity, and irradiation levels are included. Concerning the cooling systems: process water control, pressure drip studies, purging studies, corrosion, and gun barrel clearance of expanded graphite are discussed. (GHH)
Redox Committee: Conference notes and recommendations, meeting of May 16, 1949
No Description Available.
Technical Department letter, weekly, May 18, 1944--July 6, 1944
This report contains work summaries for the week of May 18th, 1944 at the Hanford Atomic Products Operation. Canning, stack gas disposal, and graphite testing are discussed. (JL)
Hanford Works monthly report, April 1949
This document details activities at the Hanford Works during the month of April 1949.
100-F unit purge May 20, 1945
No Description Available.
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