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Attempts to Delineate Inborn Anemias in Mice. Progress Report and Fifth Renewal Proposal, Report Period: January 10, 1959-January 31, 1960. Renewal Period: May 1, 1960-April 30, 1961
During the past year, three papers covering results of a major series of experiments on intergenotype of blood-forming tissue have appeared, demonstrating successful implantation of isologues normal cells in anemic hosts, permanently correcting their genetic defect in hematopoiesis, both with and without irradiation of the host. Heavy host irradiation was shown ineffective as preparations for implantation of homologous cells of widely different antigenic types.
Date:
February 16, 1960
Creator:
Russell, Elizabeth Shull, 1913-2001
Object Type:
Report
System:
The UNT Digital Library
Thorium Bismuthide : Ultrasonic Control of Crystal Size
Thorium bismuthide when crystallized from a solution i bismuth results in large platelets which may be as large a 1 centimeter in diameter. A slurry of these platelets is difficult to pump through pipe lines and filters. The particle size can be reduced by (1) very rapid cooing (approximately 1000 degree C per second) or (2) ultrasonic treatment. The latter, much easier to attain in large scale, gives equiaxed particles of thorium bismuthide.
Date:
March 16, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Periodic Radiation Survey. Section I. EFPH-5465.2. Second Performance. Core I, Seed 1. Test Results DL-S-231, T-612394
The purpose of the test was to determine the radiation levels in a Reactor Plant Boiler Compartment with the respective loop shut down and the remainder of the plant operating at power. The highest radiation levels recorded in the IC Boiler Compartment were located in the vicinity of the reactor coolant loop pipe penetrations of the Compartment. Except for the above mentioned areas, personnel could continuously occupy the IC Boiler Compartment without exceeding the maximum dose rate of 300 mr per week. The areas in the vicinity of the reactor coolant pipe penetrations, however, could be occupied only 1 to 2 hours per person per week because of the high radiation levers (200-250 mr/hr) present at these locations.
Date:
December 16, 1959
Creator:
McTish, James M.
Object Type:
Report
System:
The UNT Digital Library
Development of a Beta-Ray Particle Size Analyzer : Progress From November 15 to December 14, 1959
Monthly letter report on the research on the development of a beta-ray particle size analyzer (BPSA).
Date:
December 16, 1959
Creator:
Hewitt, Eric J.
Object Type:
Report
System:
The UNT Digital Library
Particle Extraction III
A device to extend the operation of a beam extraction system is described for low energies where the radiation loss per turn is ineffective. The device consists of a noisy radiofrequency field which excites the radial betatron oscillation
Date:
February 16, 1959
Creator:
Robinson, Kenneth W.
Object Type:
Report
System:
The UNT Digital Library
Revised Version of HFIR Critical Experiment-2 (HFCE-2)
A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date:
January 16, 1961
Creator:
Kasten, P. R. & Cheverton, R. D.
Object Type:
Report
System:
The UNT Digital Library
Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents
The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date:
December 16, 1960
Creator:
Pierce, R. M.
Object Type:
Report
System:
The UNT Digital Library
FORE - A Computational Program For The Analysis Of Fast Reactor Excursions
A digital computer program, FORE, which calculates transients for a fast reactor, has been coded for the TRANSAC 2000 computer. Its purpose is to provide understanding of the dynamics of fast reactors with particular emphasis on large ceramic-fueled fast reactors. The program calculates reactor power and temperatures of fuel, coolant, clad, and structure.
Date:
October 16, 1962
Creator:
Greebler, P.; Sherer, D. B. & Walton, N. H.
Object Type:
Report
System:
The UNT Digital Library
Safeguard Report For Open Pool Reactor For State College of Washington
This report presents the reactor description and safeguard evaluation for an open pool research and test reactor being supplied to the State College of Washington, Pullman, Washington, by the General Electric Company.
Date:
February 16, 1959
Creator:
Holzmann, E. G.
Object Type:
Report
System:
The UNT Digital Library
Analysis of Thorex Pilot Plant Radiation Exposures During 1955
The Thorex Pilot Plant at Oak Ridge National Laboratory was operated during 1955, processing reactor-irradiated thorium slugs to recover U233 and thorium and 12 MTR fuel elements to recover U235 and Np237. The radiation exposure received by operating personnel during this period averaged 60 mrcp/man-week. Most radiation exposure was received in areas that were intended to be only slightly or nonradioactive. However, because insufficient decontamination of process solutions was achieved and equipment surfaces became contaminated from equipment failures, these areas became primary sources of personnel exposure. The installation of additional shielding where needed and the prompt removal of surface contamination successfully reduced the radiation levels and exposures in these areas. Remote control of processing equipment and sampling of very radioactive solutions from process equipment was successfully accomplished, and assisted in the reduction of exposure to operating personnel.
Date:
November 16, 1956
Creator:
McCarley W. T.
Object Type:
Report
System:
The UNT Digital Library
Solid State Division Semiannual Progress Report for Period Ending August 31, 1955
LITR Fluoride-Fuel Loop. — The inconel loop was dismantled for removal of the samples and for recovery of the uranium by using the remote cutting tools installed in a half cell of the Solid State Building. Disassembly proceeded without incident. An electric-arc cutting technique was developed for removal of the stainless steel enclosure around the pump bowl. Fission power and maximum flux were determined by irradiating a simulated loop, by heat-balance calculations, by radiochemical analyses for fission products in the fuel, by measuring the activation of cobalt foils attached to the loop, and by activation of the loop tubing itself. The determination of the power by these various methods gave 2.5 to 2.8 kw during operation of the loop, and the maximum power density was 0.4 kw/cc. Chemical analyses of the fuel were carried out to determine U, Zr, and the major constituents of inconel: Ni, Cr, and Fe.
Date:
November 16, 1955
Creator:
Billington, D. S. & Crawford, J. H., Jr.
Object Type:
Report
System:
The UNT Digital Library
Statistical Evaluation of Methods for the Analysis of Dibasic Aluminum Nitrate (DIBAN)
The indicated methods for determining the following constituents of Diban, which is an aqueous solution of dibasic aluminum nitrate, Al(OH)2NO3, were evaluated statistically: 1aluminum by gravimetric, volumetric, and spectrophotometric procedures, 2. basicity (hydroxyl value) by formation of an aluminum complex and titration of the free acid with standard alkali solution, 3. total nitrogen by the Kjeldahl method, 4. ammonia by the Kjeldahl method, and 5. nitrates by means of a cation-exchange resin and titration of the liberated acid with standard alkali solution. Recommendations are made regarding the preferred methods of determining the constituents in dibasic aluminum nitrate and regarding means of minimizing errors in these analyses.
Date:
September 16, 1955
Creator:
Surak, J. G.; Thomason, P. F. & Haaen, H. P.
Object Type:
Report
System:
The UNT Digital Library
Products Produced in Continuous Neuron Irradiation of Thorium
Calculated data and graphs describing the effects of continuous thermal-neutron irradiation of thorium, the usual method of operations of homogeneous reactors, are presented.The buildup and decay of U^233, Pa^233, other heavy isotopes, and fission products are considered on the basis of best available cross-section and fission-yield data. The effects of the heavy isotopes and fission products on neutron economy are discussed.
Date:
February 16, 1956
Creator:
Gresky, A. T. & Arnold, E. D.
Object Type:
Report
System:
The UNT Digital Library
Internal Bunching in the Alternating Gradient Synchrotron (AGS)
Four methods of rebunching protons within Brookhaven's AGS are discussed. The first method involving switching off the old r-f and switching on the new r-f simultaneously with the new r-f increasing adiabatically seems impractical. Two other methods utilize gradual removal of the old r-f voltage and introduction of the new r-f voltage, or the reverse. Removal of the old r-f voltage followed by introduction of the new seems to give the best results. Several phase diagrams are included. (D.C.W.)
Date:
January 16, 1961
Creator:
Robertson, D. S.
Object Type:
Report
System:
The UNT Digital Library
Use of Isolated Junction Sheathed Thermocouples for Moderator Temperature Measurements
Two types of enclosed hot junction arrangements are possible with sheathed mineral insulated thermocouples. They are the integral junction and he isolated junction. The integral junction is formed by welding, soldering, brazing or forging the two wires into the end of the sheath. The process forms a good thermal and electrical contact between the three materials.
Date:
June 16, 1960
Creator:
Lovett, D. B.
Object Type:
Report
System:
The UNT Digital Library
Magnetic-Force Resistance Butt Wielding of Zircaloy-2 Fuel Element Closures
Zircaloy-2 has a strong tendency to absorb oxygen and nitrogen at elevated temperatures. These gas impurities are extremely harmful, causing brittleness and loss of corrosion resistance. The production of ductile corrosion-resistant welds by present methods required shielding of the weld metal by an inert gas atmosphere or by a vacuum. The alternative to an inert gas atmosphere or a vacuum is reduction of the welding time to a few milliseconds of time to prevent gas absorption.
Date:
November 16, 1959
Creator:
Mills, L. E.
Object Type:
Report
System:
The UNT Digital Library
Minutes of Criticality Instrumentation Meeting Hanford Atomic Products Operation August 17 and 18, 1959
At the request of the Hanford Operations Office of the Atomic Energy Commission, a criticality instrumentation meeting was held at Hanford on August 17 and 18, 1959. The purposes of the meeting were: (a) to review types of criticality control and/or alarm instrumentation at each site, their problems, shortcomings and potential obsolescence; (b) to discuss instrumentation in the area if approaching criticality; and (c) to consider for material balance purposes, the feasibility of devising instruments to detect the buildup of plutonium and enriched uranium bearing residues in process systems.
Date:
September 16, 1959
Creator:
Brown, C. L.
Object Type:
Report
System:
The UNT Digital Library
Recovery of Plutonium and Neptunium from Purex IWW by Anion Exchange
The recovery of plutonium and neptunium by anion exchange has been well demonstrated on a laboratory scale. (1, 2,3,4) The specific adsorbed by the resin is the tetravalent hexanitrate complex of either element. With plutonium (IV) and neptunium(V) in IWW, the plutonium is adsorbed but the neptunium is not. If nitrite is used as the reductant in strong (preferably 8 M or over) nitric acid, both plutonium and neptunium are obtained in the tetravalent state, and both are adsorbed on the resin. With stronger reductants, such as semi carbazide or ferrous sulfamate, plutonium (III) and neptunium (IV) are obtained so that only the neptunium is adsorbed. Optimum recovery of either element is obtained with between seven and eight M nitric acid.
Date:
July 16, 1959
Creator:
Van Tuyl, H. H.
Object Type:
Report
System:
The UNT Digital Library
Physics Division Quarterly Report : November, December, 1952 and January, 1953
Report on UCRL progress in general physics research and accelerator operation and development.
Date:
March 16, 1953
Creator:
University of California Radiation Laboratory
Object Type:
Report
System:
The UNT Digital Library
Physics Division Quarterly Report - May, June, and July, 1952
Physics Division quarterly report - general physics research projects and accelerator operation and development.
Date:
September 16, 1952
Creator:
University of California Radiation Laboratory
Object Type:
Report
System:
The UNT Digital Library
Hydromagnetic Ionizing Waves
It is possible to generate a relatively uniform, highly ionized plasma by passing a powerful discharge between electrodes so arranged that the current is forced to flow across an initial strong magnetic field. The magnetic induction due to the discharge causes a bending of the original field. If the discharge is operated with a low-impedance current source, the electric breakdown starts in a limited region near the current-input connections (minimum-inductance path) and propagates as a well-defined front in the manner of a hydromagnetic shock wave. In this paper we analyze the phenomenon as a one-dimensional single-fluid hydromagnetic problem, neglecting dissipation behind the wave.
Date:
May 16, 1961
Creator:
Kunkel, Wulf B. & Gross, Robert A.
Object Type:
Report
System:
The UNT Digital Library
Digital-Computer Analysis Of Data From Bubble Chambers. IV. The Kinematic Analysis Of Complete Events
A digital computer program called KICK (K-meson Interaction Coplanarization and Kinematics), which carries out the analysis of complete bubble chamber events, is described.
Date:
February 16, 1960
Creator:
Rosenfeld, Arthur H., 1926-2017 & Snyder, James N.
Object Type:
Report
System:
The UNT Digital Library
Organic Continuous Cartridge for the Purex 2D Column
This document covers work done in 3- and 4-inch-diameter glass columns directed toward the development of improved cartridges for the Purex Plant final uranium cycle extraction column, the 2D column. A nozzle plate cartridge for the extraction section and a mixed plate cartridge containing both stainless steel and fluorothene sieve plates for the scrub section were developed. In 3- and 4-inch-diameter glass columns these cartridges have a uranium extraction efficiency as good as or better than the present cartridge; and a scrubbing efficiency, based on the transfer of chloride ion, about the same as the present cartridge.
Date:
October 16, 1956
Creator:
Hesson, G. M.
Object Type:
Report
System:
The UNT Digital Library
A Preliminary Study of the Mechanical Properties of M-388, An Aluminum - 1% Nickel Alloy
M-388 is an aluminum alloy consisting of 2S aluminum with an addition of 1% nickel. Preliminary corrosion studies which were conducted by Dreley and by Dillon indicated that the material exhibited excellent resistance to intergranular type of corrosion in distilled water at temperatures of up to 350 C. The combination of a low thermal neutron cross-section and good corrosion resistance make M-388 alloy a candidate material for use in reactor process tubes and fuel element cans. The purpose of the study was to determine some of the mechanical properties of M-388 aluminum alloy at room temperature and at elevated temperatures.
Date:
March 16, 1956
Creator:
Johnson, D.E. & Ellis, W.E.
Object Type:
Report
System:
The UNT Digital Library