Resource Type

Texas Attorney General Opinion: WW-386 (open access)

Texas Attorney General Opinion: WW-386

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: Constitutionality and Construction of Portions of the Adult Probation and Parole Law of 1957.
Date: March 11, 1958
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-447 (open access)

Texas Attorney General Opinion: WW-447

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: Whether a domestic or foreign corporation may qualify in Texas to act as the general agent of an insurance company other than a life insurance company.
Date: June 11, 1958
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-499 (open access)

Texas Attorney General Opinion: WW-499

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: Authority of the State Board of Control to modify and alter the permanent entrances into the Capitol grounds.
Date: September 11, 1958
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Development of Cermet Fuel Elements (open access)

Development of Cermet Fuel Elements

Abstract: "Fabrication techniques for making metal-ceramic fuel elements containing 60 to 90 volume per cent of UN or UO2 in a Type 302B stainless steel matrix was investigated. A hot press-forging procedure was most successful for fabricating fuel cores with a density of 90 per cent of theoretical or better. This procedure consisted of sealing the cold-pressed core compacts in stainless steel picture-frame packs, heating to 1900 F, and pressing to a total reduction in thickness of 35 per cent. A pressure of approximately 50 tsi ores used. Specimens produced by this method were evaluated on the basis of their microstructure, modules if rupture, electrical conductivity, and resistance to thermal shock. Microscopic and macroscopic examination showed the presence of a continuous metal skeleton even in specimens containing 90 volume per cent fuel. The modulus of rupture at room temperature varied from 22,500 psi for a specimen cnotaining 63 volume per cent UO2. Both the electrical conductivity and resistance to thermal shock of UO2 were improved by the addition of a small volume of metal. Gas-pressure-bonding techniques appear promising for clodding these cores into composite elements."
Date: August 11, 1958
Creator: Paprocki, Stan J.; Keller, Donald L.; Cunningham, G. W. & Kizer, Donald E.
Object Type: Report
System: The UNT Digital Library
External Environmental Radiation Measurements in the United States (open access)

External Environmental Radiation Measurements in the United States

Report regarding ion chamber measurements made of the external environmental radiation in various location in the United States during the summer of 1957.
Date: March 11, 1958
Creator: Solon, Leonard R.; Lowder, Wayne M.; Zila, Albert; LeVine, H. D.; Blatz, Hanson & Eisenbud, Merril
Object Type: Report
System: The UNT Digital Library
Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores (open access)

Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores

A series of two-group calculations has been made on the Oracle for the purpose of obtaining critical-mass and flux distribution data for various ORR core configurations. The 3G3R code of Bate, Einstein, and Kinney was used, together with the RSP code developed by Nelson. This made it possible to obtain results for the three-dimensional case. The results, which are presented graphically, are intended to serve as a guide for the design of experiments until such time as actual measurements are available. The calculations were performed for the "clean cold" case, and it should be realized that the presence in the core of experiments and of fission products built up during operation will materially alter the flux patterns found. It is believed that the critical-mass data are accurate to within 10%. Within the fuel region it is believed that the thermal-flux patterns are the also accurate to this degree. Comparison of the results with MTR critical experiments, however, indicates that the thermal flux in the reflector in the vicinity of the fuel-reflector interface may have been underestimated by a factor of as much as 1.3. It should also be recalled that in a two-group calculation the "fast flux" is often a …
Date: March 11, 1958
Creator: Binford, F. T.
Object Type: Report
System: The UNT Digital Library
Experiments on the Release of Fission Products from Molten Reactor Fuels (open access)

Experiments on the Release of Fission Products from Molten Reactor Fuels

Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types, have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of rare gases, iodine, bromine, cesium, and rubidium. In the presence of air or water vapor, strontium and other fission products are not released. At trace concentration of fission products, slow melting of the APPR plate at 1525 C in air or steam effected the release of 50% of the rare gases, 33% of the iodine, 9% of the cesium, and traces of strontium. After 25% burn-up, the cesium value increased to about 60%. Aluminum alloy of the MTR type, also at trace concentration, upon melting at 700 C released up to 2% of the iodine, 10% of the rare gases, and negligible portions of other fission products. Zirconium alloy of the STR type after 15% burn-up, when melted at 1850 C, released up to 95% of the rare gases, 90% of …
Date: March 11, 1958
Creator: Parker, George W. & Creek, George E.
Object Type: Report
System: The UNT Digital Library