UNT Libraries Government Documents Department - 15 Matching Results

Search Results

Applied Health Physics Annual Report for 1963
Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Aging Characteristics of Hastelloy B
Report issued by the Oak Ridge National Laboratory discussing the aging characteristics of the alloy Hastelloy B. Materials, equipment, experimental procedures, and results used to determine the characteristics of the alloy are presented. This report includes tables, illustrations, and photographs.
Production Separations of Fission-Product Groups for the Radioisotope Program
Report issued by the Oak Ridge National Laboratory discussing the production separation for the radioisotope program. As stated in the abstract, "a general description is given of five years' experience in routine production of fission products of high concentration and high activity levels for the radioisotope program. Details of construction and production processes are given for two systems which were built on ion-exchange principle" (p. 2). This report includes illustrations, and photographs.
Homogeneous Reactor Project Quarterly Progress Report: February-April 1959
Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables
Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962
Report that describes the research and developments of the Nuclear Safety Research and Development Program of the Oak Ridge National Laboratory.
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings
Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
A Revision of Computer Code POWERCO (Cost of Electricity Produced by Nuclear Power Stations) to Include Breakdowns of Power Cost and Fixed Charge Rates
Report that "describes a new version of the code, POWERC-50, which contains several changes" to the previous code, POWERCO-25, which was used to calculate "the levelized cost of electricity produced by nuclear power stations" (p. 1)
The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah
Report containing a survey of the radiation from the nuclear ship Savannah in order to determine the dose rate for people aboard.
Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1971
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C
Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962
From introduction: "This is the eleventh of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1
First volume of a compilation of information about reactor containment, written by experts from a variety of organizations.
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Homogeneous Reactor Project Quarterly Progress Report: February-April 1960
Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.