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Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 2
Second volume of a compilation of information about reactor containment, written by experts from a variety of organizations.
EVESR Nuclear Superheat Fuel Development Project: First Quarterly Report, May 4-August 31, 1962
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
EVESR Nuclear Superheat Fuel Development Project: Second Quarterly Report, September-November 1962
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
Fuel Cycle Program Progress Report: Fifteenth Report, January-June 1964
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962
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).
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fifth Quarterly Report, October-December 1962
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).
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).
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963
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).
EVESR Nuclear Superheat Fuel Development Project: Third Quarterly Report, December 1962-February 1963
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
Steam-Cooled Power Reactor Evaluation for 300 MW(e) Separate Superheater Reactor
From introduction: "This report provides the preliminary design for the nuclear portion of a 300 MWe Boiling Water Separate Superheater Plant to be in operation by 1967."
Southwest Experimental Fast Oxide Reactor Development Program: First Quarterly Report, April-June 1964
From abstract: "This report summarizes the work performed on the Research and Development Program for the Southwest Experimental Fast Oxide Reactor."
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.
Nuclear Merchant Ship Reactor Final Safeguards Report, Volume 6: Environmental Analysis OF NS "Savannah" Operation at Camden
"An analysis is presented of the accidental release of activity following the operation of the NS "Savannah" at the New York Shipbuilding Corporation docks in Camden, New Jersey. Although a number of accidents are considered, the report is primarily concerned with the environmental activity levels and subsequent exposures which would result from the "maximum credible accident" (p. v).
The Preparation and Properties of Mammalian Ribonucleic Acids
"A method for the preparation of mammalian ribonucleic acids employing high concentrations of guanidine hydrochloride in the fractionation procedure is reported in this paper. Aside from the facility of preparation the method has the advantage of avoiding conditions of acidity and alkalinity which might degrade tissue ribonucleic acids and, by virtue of the protein denaturant action of guanidine salts, of minimizing the possibility for enzymatic degradation" (p. 3).
Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR
From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."
The Effects of Internal Heat Generation on Pot Calcination Rates for Radioactive Wastes
Review of methods by which the radial deposition mechanism was determined in experiments with simulated waste solutions are briefly reviewed.
A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator
Abstract: "The Oak Ridge National Laboratory proposes to build an isochronous eight-sector proton cyclotron to provide an extracted beam in excess of 100 A at 810 MeV. The primary proton beam and the secondary meson and neutron beams will be used to investigate nuclear structure, and the interactions between elementary particles. Biomedical and Space-oriented research programs are also planned. Shielded research areas and an extensive beam transport and analysis system are provided. Theoretical and experimental studies have shown that the Mc2 Cyclotron is a practical concept; high extraction efficiencies can be obtained, and the residual radiation problems are manageable. The project would require less than seven years to complete, and would cost about $43,000,000."
The High Flux Isotope Reactor: A Functional Description, Volume 1, Illustrations
Report containing illustrations of the high-flux isotope reactor.
Molten-Salt Reactor Program Quarterly Progress Report: October 1959
Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Radiation Stability Studies
From abstract: "An investigation of the radiation stabilities of aqueous solutions of sodium ethylenediamine tetraacetate and sodium acetate was made using a 3000-curie Co⁶⁰ source...A study of the behavior of the standard-size Beckman type glass pH electrodes in a solution containing 0.36 curie of Ce¹⁴⁴-Pr¹⁴⁴ activity per milliliter showed the useful electrode life to be of the order of two to eight days."
Use of Steam-Electric Power Plants to Provide Thermal Energy to Urban Areas
This report presents the results of a study that argues the importance of providing thermal energy from steam-electric power plants to urban areas.