Texas Attorney General Opinion: WW-927 (open access)

Texas Attorney General Opinion: WW-927

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: Is a non-profit water supply or sewer service corporation organized pursuant to Acts 1933, 43rd Leg., 1st C.S., Chap. 76, as amended, exempt from the payment of franchise tax.
Date: August 31, 1960
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Coolant backup design study basis and objective (open access)

Coolant backup design study basis and objective

Preliminary studies have, in general, indicated the need for modifications and improvements to the reactor last ditch coolants systems in order to provide adequate safety of operation at power levels programmed for the future. These studies have indicated the need for improved reliability as well as increased capacity for the last ditch coolant systems. A design study is being prepared by Reactor Modification Design to define the scope of the modifications required to provide adequate last ditch systems for the older areas. Adequate last ditch cooling will be provided for the 100-K Areas under Project CGI-844 which is currently in progress. The purpose of this document is to set forth the operating conditions and objectives on which the study will be based.
Date: August 31, 1960
Creator: Schack, M. H. & Tupper, W. J.
Object Type: Report
System: The UNT Digital Library
Design of production test IP-344-A-FP, determination of the limitations of the Al-Si process (open access)

Design of production test IP-344-A-FP, determination of the limitations of the Al-Si process

Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can bond separation following irradiation. Such evidence has aroused concern for the ability of the currently produced Al-Si bonded fuel elements to withstand future reactor operating conditions. Several potential uranium fabrication and canning process improvements are being developed to further advance fuel element stability and performance. Optimization of process conditions based on these improvements may provide the necessary margin of safety for good bond layer integrity. Before a decision can be made to continue improvement of the present process or convert to a new canning process, more information on the stability of the present fuel element bond is needed. This report presents the design of a test to more fully evaluate Al-Si bond integrity under anticipated future reactor operating conditions.
Date: August 31, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
Object Type: Report
System: The UNT Digital Library
VORTEX: Progress report for August 1960 (open access)

VORTEX: Progress report for August 1960

None
Date: August 31, 1960
Creator: Crowley, W.B.
Object Type: Report
System: The UNT Digital Library
Adsorption of Radioactive Gases on Activated Carbon (open access)

Adsorption of Radioactive Gases on Activated Carbon

The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Date: August 31, 1960
Creator: Madey, Richard; Barker, J. J.; Beebe, M. R. & Stephenson, T. E.
Object Type: Report
System: The UNT Digital Library
Pebble Bed Friction Factor and Thermal Expansion Tests (open access)

Pebble Bed Friction Factor and Thermal Expansion Tests

Tests were conducted to determine the friction factor of randomly packed beds of 3/4-inch diameter spheres in 8-inch and 15-1/4-inch diameter beds, and of 1-1/2-inch diameter spheres in 15-1/4-inch diameter bed. The bed depths were varied in an attempt to isolate the effects of entrance and exit losses. The bed Reynolds number, base on sphere diameter, was varied from 5,000 to 50,000.
Date: August 31, 1960
Creator: Leeman, C. A.
Object Type: Report
System: The UNT Digital Library