Search Results

open access

Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

Description: From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
Partner: UNT Libraries Government Documents Department
open access

Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Trauger, D. B. & Whitman, G. D.
Partner: UNT Libraries Government Documents Department
open access

Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney

Description: Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Jones, Edith Seymour
Partner: UNT Libraries Government Documents Department
open access

Homogeneous Reactor Project Progress Report: May-October 1959

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 10, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Partner: UNT Libraries Government Documents Department
open access

Instrumentation and Controls Division Semiannual Progress Report for Period Ending July 31, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Instrumentation and Controls Division. Descriptions of progress and studies conducted are presented. This report includes illustrations, and photographs.
Date: February 25, 1957
Creator: Borkowski, C. J.
Partner: UNT Libraries Government Documents Department
open access

Homogeneous Reactor Project Quarterly Progress Report: August-October 1956

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 19, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Bruce, F. R. et al.
Partner: UNT Libraries Government Documents Department
open access

Physics Division Semiannual Progress Report for Period Ending September 10, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Physics Division. Descriptions of progress and studies conducted are presented. This report includes tables, and illustrations.
Date: February 12, 1957
Creator: Snell, A. H.; Fowler, J. L. & Wollan, E. O.
Partner: UNT Libraries Government Documents Department
open access

Stable Isotopes Division Semiannual Progress Report for Period Ending November 30, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing progress made by the Stable Isotopes Division. Descriptions of of the progress and studies made are presented. This report includes tables, illustrations, and photographs.
Date: February 12, 1957
Creator: Keim, C. P. & McNally, J. R., Jr.
Partner: UNT Libraries Government Documents Department
open access

Determination of Trivalent Uranium in Fluoride Salt Mixtures by the Modified Hydrogen Evolution Method

Description: The hydrogen evolution method for the determination of uranium trifluoride which was developed by Manning, Miller and Rowan has been used for the determination of trivalent uranium in this laboratory for the past three years. The method has been applied to many different sample types supposedly pure UF3, mixtures of UF3 and UF4 and the large variety of mixtures of fluoride salts that have been investigated as possible nuclear fuels. These mixtures contained alkali metal, beryllium and zirconium… more
Date: February 26, 1956
Creator: White, J. C.; Meyer, A. S., Jr.; Vaughan, W. F.; Ross, W. J. & Manning, D. L.
Partner: UNT Libraries Government Documents Department
open access

Chemical Separation of Isotopes Section Semiannual Progress Report for Period Ending June 30, 1955

Description: The countercurrent gas-liquid system BF3(g)—anisole·BF3(l) for the concentration of boron isotopes has been studied. The single-storage separation factor varies from 1.039 at 0°C to 1.029 at 30°C. Rate of exchange is rapid, and, with efficient contacting equipment, complete exchange may be obtained in less than 15 sec. A total separation of 1.525 has been realized in laboratory equipment. The critical-product reflux reaction is quite efficient. Only about 55 moles of BF3 remain in each million … more
Date: February 23, 1956
Creator: Clewett, G. H. & Drury, J. S.
Partner: UNT Libraries Government Documents Department
open access

Development of a Cubic Oxide Protective Film on Zirconium

Description: Observations of the effects of neutron damage to zirconium oxides led to the conclusion that the cubic form of ZrO2 is more stable to such damage than the monoclinic form. It has been reported that zirconium corrodes more rapidly in certain liquids when exposure is made under radiation (neutrons and fission products). It is well known that on heating monoclinic ZrO2 a transformation, monoclinic to tetragonal (very similar to cubic), occurs at about 1500°C. The transformation involves sufficient… more
Date: February 21, 1956
Creator: Johnson, J. R.
Partner: UNT Libraries Government Documents Department
open access

The Technology of Uranium Dioxide a Reactor Material

Description: Consideration has been given to various forms of fissionable material for use in atomic reactors, including the pure metals, their alloys and compounds. Of particular interest is the dioxide of uranium which is refractory and corrosion resistant in some environments.The oxide is useful in both granular and bulk forms. Small grains of uranium oxide can be mixed with other materials to form matrix type elements where they serve either as a convenient or necessary form of fuel or fertile material.… more
Date: February 21, 1956
Creator: Johnson, J. R.; Doney, L. M.; Fulkerson, S. D.; Taylor, A. J.; Warde, J. M. & White, G. D.
Partner: UNT Libraries Government Documents Department
open access

Products Produced in Continuous Neuron Irradiation of Thorium

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures

Description: The enthalpies and heat capacities of seventeen fluoride mixtures in the liquid state have been determined using Bunsen Ice Calorimeters and copper block calorimeters. The fluoride mixtures were composed of the fluorides of two or more of the following metals: lithium, sodium, potassium, beryllium, zirconium, and uranium. The enthalpies and heat capacities of most of these mixtures were studied in the solid state also. Estimates of the heat of fusion have been made. General empirical equations … more
Date: February 1, 1956
Creator: Powers, W. D. & Blalock, G. C.
Partner: UNT Libraries Government Documents Department
open access

A Monte Carlo Estimation of the High Energy Neutron Flux Distribution in the ORNL Graphite Reactor

Description: The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estima… more
Date: February 23, 1955
Creator: Moshman, Jack
Partner: UNT Libraries Government Documents Department
open access

Stable Isotope Research and Production Division Semiannual Progress Report

Description: The Spectroscopy Research Laboratory is concerned with research and development in the fields of nuclear magnetic resonance, microwaves, infrared and optical spectroscopy, spectrochemistry, and x rays. Research is directed toward fruitful methods of isotope analysis; new element and compound analytical methods having application to immediate Laboratory or long-range commission needs; and fundamental research on isotopes, elements, and compounds. The work is reported on a project basis to give a… more
Date: February 18, 1955
Creator: Keim, C. P.
Partner: UNT Libraries Government Documents Department
open access

A Low Cost Experimental Neutron Chain Reactor Part 2

Description: Description of cooling, shielding, controls are discussed for 100 kw and 1 Mw operation of a low cost experimental neutron chain reactor.
Date: February 5, 1954
Creator: Abernathy, Fred H.; Barrett, Lawrence G.; Berger, William A.; Dever, John A.; Maurer, John F.; Mesler, Russell B. et al.
Partner: UNT Libraries Government Documents Department
open access

Dynamics of the Supercritical Water Reactor

Description: From introduction: "The work described in this report was carried out as part of the feasibility study (ORNL-117) of a supercritical water reactor (SCWR) for use in nuclear propulsion of aircraft. The object of this work was to study the dynamic behavior of a particular design of supercritical water reactor. Numerical results are presented in Appendix I."
Date: February 1, 1953
Creator: Goertzel, Gerald, 1919-; Shapiro, Mathew M. & Soodak, Harry
Partner: UNT Libraries Government Documents Department
Back to Top of Screen