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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959

Description: Introduction: "This is the seventh letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from April 1 to May 31, 1959."
Date: June 15, 1959
Creator: Stockham, John D. & Rosinski, John
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Magnetic Recorder for Nuclear Pulse Application : Covering the Period from August 6, 1959 to October 5, 1959

Description: The following report discusses direct recording of nuclear pulse height data on magnetic tape that represents an inexpensive method of data storage where some degradation of the original energy resolution can be tolerated.
Date: October 15, 1959
Creator: Burgwald, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Creep and Relaxation in Metals and Ceramics : A Bibliography, 1950-March 1959

Description: "This is a selected bibliography of books, journal articles and reports published on creep and relaxation in metals and ceramics from 1950 to March 1959. Particular attention has been paid to studies on or applicable to the consideration of creep and relaxation in beryllium oxide. Emphasis has alro been placed on studies of phenomenological materials behavior and high temperature studies."
Date: April 15, 1959
Creator: Maynard, Glenn R. & Lane, Zanier D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ionium Recovery Plant Design Report: Topical Report

Description: This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
Date: April 15, 1959
Creator: Edwards, R. M.; Fariss, R. H. & Werkema, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Oxygen in Oxide Films by Neutron Activation Analysis

Description: Preliminary experiments have been conducted to evaluate the use of the nuclear reactions Li6 (n,α)H3 and O16(H13,n)F18 to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10^11 n/cm^2/sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F18 of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities ma… more
Date: July 15, 1959
Creator: Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Containment Properties of DCX

Description: The "absolute" containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confinement in space and momentum are plotted for 300 Kev deuterons.
Date: June 15, 1959
Creator: Fowler, T. K. & Rankin, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ionium (Thorium-230) for Radioisotope Preparation (Status Report)

Description: For many years effort has been directed toward the development of means for the practical utilization of the heat evolved from the radioactive decay of certain fission and irradiation products. Fission products, in view of their availability in the plentiful, high-level wastes resulting from the processing of irradiated, nuclear reactor fuels have been most intensively studied for applications where their heat of decay might be converted into useful energy such as electricity for the operations… more
Date: December 15, 1959
Creator: Coppinger, E. A. & Rohrmann, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Report- August 1959

Description: Sinterability studies on mixtures of UO2 and PuO2 powders have been continued. All of the censities from previous sintering experiments have been recalculated utilizing a somewhat different water immersion technique. Since densities of pellete obtained by physical dimensions are inaccurate due to chipping, and water immersion does not account for the open porosity, the pellets were coated with clear krylon before being immersed in water. This effectively sealed the open pores. Plots of density … more
Date: September 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRTR High Pressure Loop Hazards Survey of Preliminary Scope Design

Description: Conceptual design studies conducted at HAPO indicate that the improved thermal efficiencies which can be obtained in a high pressure, high temperature, nuclear-electric power plant might reduce unit power costs substantially. The Plutonium Recycle Test Reactor (PRTR) is designed primarily to investigate various facets of plutonium recycle operation. In order to increases the usefulness of the PRTR as an experimental tool, it is desirable to include facilities for testing materials and fuel conc… more
Date: October 15, 1959
Creator: Walkup, P. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report - February 1959

Description: Plutonium Oxide Fuels. Mixtures of PWR grade UO2 containing 10, 20, 30, 40, 50, and 60 w/o PuO2 were sintered in hydrogen for 44 hours at 1600 C to get additional data on solubility in this system. Densities of all the pieces were low, approximately 80 percent of theoretical; however, solid solution formation was complete in every case. The low density material should not affect lattice parameter values, but it did slightly reduce the intensity of the reflections.
Date: March 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report- May 19599

Description: Plutonium Fuels Development Basic studies. Experiments to determine the effect of plutonium dioxide additions on the sinterability of UO2 have continued. PuO2 has been added to ball milled PWR grade UO2 as a physical mixture, and in the form of the mixed crystal oxide.
Date: June 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Water Temperatures for the Columbia River Above the Hanford Reactors, September, 1946 Through December, 1958

Description: The ambient temperature of the Columbia River is of interest to the Aquatic Biology Operation since it provides a basis for controlling the temperatures in various experimental tanks which contain Columbia River organisms and since it provides some indication of whether conditions are favorable for the valuable species of fish living in the river. Since the start-up of the plant, temperatures of the river water have been taken in the several water treatment plants.
Date: April 15, 1959
Creator: Foster, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report- March 1959

Description: Basic Studies. It has been reported previously that mixed crystals of PuO2 and UO2 have a higher sintering rate than UO2 alone. However, results to the contrary were obtained on addition to 1/4, 1/2, 1, 2, 5, and 10 w/o PuO2 to PWR grade UO2. Pellets of the above concentrations were heated for one hour in hydrogen at 100 C intervals from 1000 to 1600C.
Date: April 15, 1959
Creator: Hanford Laboratories Operation Fuels Preparation Department, Irradiation Processing Department
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report- December 1958

Description: Two Zircaloy-clad capsules (GKH-14-19,20) containing two compacts each of high density PuO2-UO2 mixed crystal oxides were shipped to the MTR in December 2, 1958. The compacts contain 0.026 a/o PuO2, have densities of 91 percent of the theoretical value, and will generate the same specific power as an Al-1.8w/o Pu alloy rod of the same diameter would produce. Two capsules (GKH-14-21,22) have been prepared and contain three compacts each of low density, about 65 percent of the theoretical value, … more
Date: January 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Criteria for PRTR High Pressure Loop Project CAH-841

Description: The PRTR pressure loop is an experimental facility to be installed in the Plutonium Recycle Test Reactor, Building 309, for use in testing the feasibility of reactor cooling systems utilizing high pressure water or steam as the coolant. It will furnish operating experience with such systems and serve to test fuel elements and components designed to operate in such environments.
Date: October 15, 1959
Creator: Fox, J. C.; Jakub, M. T. & Kelly, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Reports-June 1959

Description: Basic Studies. Sinterability experiments in the system UO2-PuO2 have continued, and data are available at one hour hold times across the UO2-PuO2 composition limits. Sintered densities appear to be markedly dependent on pressed densities with densification occurring very rapidly at higher pressing pressures. The following table illustrates the effect of one hour at temperature on final density for pure plutonium dioxide pressed to both 40 and 60 percent of theoretical density.
Date: July 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comments on Engineering Review of PRTR by Atomic Power Equipment Department

Description: On a project of the magnitude and complexity of the Plutonium Recycle Test Reactor is was considered prudent engineering practice to obtain an independant design review by a competent off-site group that had not participated in any way in the development of the design. Accordingly, the Atomic Power Equipment Department of the General Electric Company was requested to make such an engineering review, and an Assistance to Hanford contract authorizing this work was approved by the Atomic Energy Co… more
Date: October 15, 1959
Creator: Reactor and Fuels Researcg and Development Operation Hanford Laboratories Operation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydraulic Instability In a Natural Circulation Loop With Wet Steam Generation at 1000 PSIA

Description: Experimental test loops have been used to study the problem of hydraulic stability. The oscillatory behavior of a single-phase and two-phase natural circulation loop has been examined at atmospheric pressures and oscillating modes of operation were studied in terms of heat input.
Date: July 15, 1959
Creator: Levy, S. & Beckjord, E. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Post-Irradiation Examination of Cored, Edge Loaded, Thoria-Urania Nuclear Fuel

Description: Three edge loaded thoria-urania nuclear fuel samples were assembled into a capsule, irradiated and examined. This irradiation was the first of a series to develop thoria-urania fuel for high heat flux, specific power and burn-up operation in a sodium graphite reactor.
Date: July 15, 1959
Creator: Slosek, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Collected Methods for Analysis of Sodium Metal

Description: Methods for analyzing chemical impurities in sodium metal samples are presented. Chemical analysis was used to determine the following impurities: Calcium, Carbon, Chromium, Iron, Lithium, Nickel, Oxygen, Potassium, and Zirconium. Spectrographic analysis was used to determine many other impurities. Sodium samples obtained from experimental apparatus operated as part of the work being conducted for Atomics International were analyzed by these methods.
Date: October 15, 1959
Creator: Perrine, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Powered Tanker Design and Economic Analysis - Direct Cycle Boiling Water Reactor

Description: A design and economic analysis is presented for a 44,000 DWT tanker utilizing a 27,300 shp direct cycle boiling water reactor propulsion system. Included are design descriptions and drawings, estimates of operating and capitol costs for the reference ship, estimates of long range potential, descriptions of required research and development programs, a preliminary safeguards analysis, an analysis of ship's motion on boiling water reactor performance, a summary reactor physics analysis, and a dis… more
Date: December 15, 1959
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interpretation of Westwood, New Jersey Rainfall Data

Description: "Progress is reported in an evaluation of fission product concentration in rain as a function of time, location, and meteorological setting. Data on rainfall collected at Westwood, N. J., were analyzed for information on the mechanisms of fallout deposition, seasonal variations in fallout, the stratospheric residence time of W/sup 185/ resulting from Operation Hardtack, and the accuracy of pot samplers for sample collection. Data from other collection stations were also analyzed for consistency… more
Date: September 15, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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