Resource Type

States

Month

Texas Attorney General Opinion: WW-626 (open access)

Texas Attorney General Opinion: WW-626

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Classification for inheritance tax purposes of alleged adopted child.
Date: May 20, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
NUCLEAR AND RADIATION HAZARDS EVALUATION OF SRE FUEL PROCESSING AND STORAGE (open access)

NUCLEAR AND RADIATION HAZARDS EVALUATION OF SRE FUEL PROCESSING AND STORAGE

Results are presented of an evaluation of nuclear safety and raaiation control related to the shipment, mechanical processing, and storage of SRE-1 fuel elements. (auth)
Date: May 20, 1959
Creator: Suddath, J. C.
Object Type: Report
System: The UNT Digital Library
Survey: Oxidation Characteristics of Columbium and Columbium Base Alloys (open access)

Survey: Oxidation Characteristics of Columbium and Columbium Base Alloys

Unclassified experimental data concerned with the oxidation characteristics of Nb and Nb-base alloys are presented. The bulk of the results is presented in tabular form and cataloged under laboratory name sub-headings. The theory of alloy development for oxidation resistance is discussed. Methods of evaluating oxidation behavior are outlined.
Date: May 20, 1959
Creator: Clough, W. R. (William Raymond); Hirakis, E. C. & Krutenat, R. C.
Object Type: Report
System: The UNT Digital Library
Investigation Of Windows And Shields For Neutron Point Sources (open access)

Investigation Of Windows And Shields For Neutron Point Sources

An empirical approach for the evaluation of shielding materials for macrochemical manipulations of spontaneously fissioning heavy elements (curium and californium) has revealed interesting comparisons. High-density metal halide solutions were compared with lead glass and with rare earth glass for use as shielding windows. Laminated shields of lead-paraffin and uranium-paraffin were compared with water and with paraffin for shielding walls.
Date: May 20, 1959
Creator: Browne, Howard J.; Kaufmann, John A. & Garden, Nelson B.
Object Type: Report
System: The UNT Digital Library
Parameters of Dissolver Equipment Design - Power Fuel Reprocessing (open access)

Parameters of Dissolver Equipment Design - Power Fuel Reprocessing

The Interim Power Fuels Reprocessing Program, as established by the Atomic Energy Commission, provides the service of recovering uranium, thorium, plutonium, etc., from irradiated fuels discharged from non-production reactors of both public and private ownership. To provide this service on an interim basis and at minimum capital investment, the Commission has assigned the processing responsibility for the various fuel types to several AEC sites. The sites are to be assigned fuel types most similar to their normal production. As a result, HAPO has been assigned the responsibility for processing the low enrichment uranium and uranium oxide type fuels with isotopic content up to 5% uranium-235. In addition, some plutonium base fuels will be processed at Hanford.
Date: May 20, 1959
Creator: Graf, W. A.
Object Type: Report
System: The UNT Digital Library
The Rhode Island and Providence Plantations Atomic Energy Commission Nuclear Science Center Volume II - Safeguard Report (open access)

The Rhode Island and Providence Plantations Atomic Energy Commission Nuclear Science Center Volume II - Safeguard Report

This report presents the description and safeguard evaluation of an open pool research and test reactor rated at one megawatt. The reactor is being proposed by the General Electric Company to the Rhode Island and Providence Plantation Atomic Energy Commission.
Date: May 20, 1959
Creator: General Electric Company
Object Type: Report
System: The UNT Digital Library
Nuclear and Radiation Hazards Evaluation of SRE Fuel Processing and Storage (open access)

Nuclear and Radiation Hazards Evaluation of SRE Fuel Processing and Storage

Nuclear and radiation hazards have been investigated for all phases of operation to be carried out in the mechanical decladding of SRE fuel elements. The SRE fuel is 2.8% enriched with a maximum burnup of 1,000 Mvd/ton and minimum cooling of 120 days. Each element contains 9 kg of uranium metal (~2 kg U-235) and is made up from 84 slugs (3/4"D x 6'"), clad with (10 mil wall) stainless steel tubing. It is planned to ship the fuel from Santa Susana, California, to Oak Ridge in the modified PAR loop carriers, with a maximum of 10 elements being shipped in each carrier per trip.
Date: May 20, 1959
Creator: Suddath, J. C.
Object Type: Report
System: The UNT Digital Library