Serial/Series Title
Country
States
122 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
122
next
Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
Discussion of laboratory tests to reduce uranium corrosion.
Date:
October 14, 1964
Creator:
Sprague, T. P.; Googin, J. M. & Phillips, L. R.
System:
The UNT Digital Library
X-Ray Fluorescence Tables: Program Description
Report discussing the mechanics of X-Ray and COMBO computer programs.
Date:
July 20, 1964
Creator:
Amsbury, W. P.; Lee, W. W.; Rowan, J. H. & Walden, G. E.
System:
The UNT Digital Library
Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders
Report discussing the results of fill and drain holes for hydrostatic pressure tests on head knuckle radius of forged-steel gas storage cylinders.
Date:
November 5, 1964
Creator:
Thompson, J. C. & Lambert, F. J.
System:
The UNT Digital Library
Geophysical Seismic Evaluation Study at Hanford
From introduction: "In June, 1963, a geophysical research program was conducted at Hanford to determine the feasibility and desirability of using seismic methods in geohydrologic studies. Detection and delineation were desired of seven different geological features that in some sites affect the movement of liquid radioactive wastes discharged to the ground."
Date:
December 1964
Creator:
Brown, Ruth E. & Raymond, John R.
System:
The UNT Digital Library
PRTR second generation shim assembly
From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date:
November 1964
Creator:
Rasmussen, D. E.
System:
The UNT Digital Library
Liquid Metal Fast Breeder Reactor Design Study
From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."
Date:
January 1964
Creator:
unknown
System:
The UNT Digital Library
Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies
Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date:
1964
Creator:
Vogel, G. J.; Carls, E. L. & Mecham, W. J.
System:
The UNT Digital Library
A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys
From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.
Date:
March 1964
Creator:
Burns and Roe
System:
The UNT Digital Library
Scientific-Information Centers in the U.S.A. and the U.S.S.R
From foreword: This report provides a review of the Soviet and U.S. technical information systems.
Date:
1964?
Creator:
Kridler, Thomas P. & Simpson, G. S., Jr.
System:
The UNT Digital Library
Flow Stability of Gas-Solids Suspensions: Final Report
From abstract: One of the principal purposes of the work reported was to study the stability of gas-solids suspensions in the presence of a thermal gradient. Previously reported experience with unstable suspensions is summarized.
Date:
February 1964
Creator:
Wachtell, G. P. & Waggener, J. P.
System:
The UNT Digital Library
Evaluation of Beta Radiation as a Hydrogenation Catalyst: Interim Technical Status Report for the Period March 1, 1962 to October 31, 1963
From abstract: The concept of using high intensity beta radiation from an isotopic source, Sr-90, inside a high temperature, high pressure chemical reactor has been developed for potential radiation chemical processes. Distinct advantages include high utilizable intensity from a relatively small source with a minimum of shielding against external radiation.
Date:
September 11, 1964
Creator:
Yavorsky, P. M. & Gorin, E.
System:
The UNT Digital Library
A Study of Desalting Plants (15 to 150 mgd) and Nuclear Power Plants (200 to 1500 MWt) for Combined Water and Power Production: Final Report
From foreword: This study is concerned with the technology of producing fresh potable water from the seas.
Date:
September 1964
Creator:
Catalytic Construction Company
System:
The UNT Digital Library
A Single Stage Axial Compressor Blade Test Facility
Abstract: This report gives a general description of the single stage axial compressor blade test facility located at the Oak Ridge Gaseous Diffusion Plant, Oak Ridge, Tennessee.
Date:
January 13, 1964
Creator:
Fee, G. G.
System:
The UNT Digital Library
Analysis of Stresses in Bellows
Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date:
October 15, 1964
Creator:
Anderson, W. F.
System:
The UNT Digital Library
A Portable Neutron Counter for Determining Weights of Deposits of Uranium-Fluorine Compounds
Abstract: A high sensitivity, portable fast neutron counter has been developed for determining the weights of solid accumulations of uranium-fluorine compounds in closed process equipment.
Date:
May 11, 1964
Creator:
Stevens, R. H. & Smith, R. C.
System:
The UNT Digital Library
Criticality-Accident Dosimetry Studies
Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date:
October 15, 1964
Creator:
Bailey, J. C.
System:
The UNT Digital Library
Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications
Abstract: Under the Power Expansion Program (PEP), modifications have been made to the Sodium Reactor Experiment (SRE) facility to improve plant reliability and permit an increase in power to 30 Mwt, with a reactor coolant outlet temperature up to 1200°F.
Date:
October 9, 1964
Creator:
Freede, W. J. & Roberts, J. K.
System:
The UNT Digital Library
Operating Experience with Heat Transfer System Pumps at the Hallum Nuclear Power Facility
Introduction: It is the purpose of this report to describe the operating and maintenance experience obtained at HNPF on the sodium heat transfer pumps.
Date:
June 15, 1964
Creator:
Durand, R. E.
System:
The UNT Digital Library
Steam Cycle Optimization Study for Large Sodium Graphite Nuclear Power Generating Stations
Abstract: This report presents steam cycle optimization studies for large sodium graphite nuclear power generating stations.
Date:
August 31, 1964
Creator:
Schneider, G. A.
System:
The UNT Digital Library
UC Fuel Element Design and Fabrication
Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements.
Date:
August 1, 1964
Creator:
Draganchuk, W.
System:
The UNT Digital Library
Study of SCTI Control System
Introduction: This report has been prepared to document the extensive analytical work required to design the control system for the Sodium Components Test Installation (SCTI), constructed for the Atomic Energy Commission at the Atomics International field laboratory.
Date:
December 1, 1964
Creator:
Griffin, C. W.
System:
The UNT Digital Library
Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide
Abstract: One hundred gram quantities of uranium dioxide, irradiated to burnup as great as 21,000 Mwd/MTU and previously reprocessed by AIROX (Atomics International Reduction Oxidation), were refabricated into high density pellets and encapsulated for re-irradiation.
Date:
December 1, 1964
Creator:
Guon, J.; Bodine, J. E. & Sullivan, R. J.
System:
The UNT Digital Library
Evaluation of Coolant Impurity Removal Equipment at the OMRE
Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date:
October 15, 1964
Creator:
Barbour, P. & Davis, W. W.
System:
The UNT Digital Library
Reactor Technology Report Number 24: Metallurgy
Quarterly report issued by the Knolls Atomic Power Laboratory to report to the industry on developments in unclassified reactor technology. This issue focuses on metallurgy information.
Date:
May 1964
Creator:
unknown
System:
The UNT Digital Library