Resource Type

Texas Attorney General Opinion: S-187 (open access)

Texas Attorney General Opinion: S-187

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, John Ben Shepperd, regarding a legal question submitted for clarification: Contract for interchange of products between institutions operated by the Board for Texas State Hospitals and Special Schools.
Date: January 16, 1956
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: S-221 (open access)

Texas Attorney General Opinion: S-221

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, John Ben Shepperd, regarding a legal question submitted for clarification: Whether a retired judge may serve as County Judge and receive pay therefor, and at the same time receive benefits under the Judicial Retirement Act.
Date: November 16, 1956
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Purification of Argon, Helium and Xenon : a Bibliography (open access)

Purification of Argon, Helium and Xenon : a Bibliography

This bibliography contains 145 references on the technology and apparatus used in the purification of argon, helium and xenon, and on the analysis for water, carbon monoxide, hydrogen, nitrogen, and oxygen, in the purification process. The references are arranged in four classifications: general, argon, helium, and xenon. Within each classification, the references are arranged in chronological order.
Date: September 16, 1956
Creator: Cernak, Elizabeth A.
Object Type: Report
System: The UNT Digital Library
A Catalog of Fallout Patterns (open access)

A Catalog of Fallout Patterns

Abstract: In the event of a massive nuclear attack, the combined fallout from quantities of surface-burst nuclear weapons must be considered as a serious hazard over an extended area. This report presents one method for rapidly estimating the fallout from such an attack.
Date: April 16, 1956
Creator: Greenfield, S. M.; Rapp, R. R. & Walters, P. A.
Object Type: Report
System: The UNT Digital Library
Geologic logs of dry hole oil wells in Emery, Garfield, Grand and Kane Counties, Utah (open access)

Geologic logs of dry hole oil wells in Emery, Garfield, Grand and Kane Counties, Utah

These logs record the subsurface stratigraphy and correlate the geologic formations.
Date: August 16, 1956
Creator: Kastelie, W. E.
Object Type: Report
System: The UNT Digital Library
Organic Continuous Cartridge for the Purex 2D Column (open access)

Organic Continuous Cartridge for the Purex 2D Column

This document covers work done in 3- and 4-inch-diameter glass columns directed toward the development of improved cartridges for the Purex Plant final uranium cycle extraction column, the 2D column. A nozzle plate cartridge for the extraction section and a mixed plate cartridge containing both stainless steel and fluorothene sieve plates for the scrub section were developed. In 3- and 4-inch-diameter glass columns these cartridges have a uranium extraction efficiency as good as or better than the present cartridge; and a scrubbing efficiency, based on the transfer of chloride ion, about the same as the present cartridge.
Date: October 16, 1956
Creator: Hesson, G. M.
Object Type: Report
System: The UNT Digital Library
Exponential Pile Measurements in Water Moderated Lattices with Enriched Uranium Rods (open access)

Exponential Pile Measurements in Water Moderated Lattices with Enriched Uranium Rods

This paper presents the results of a series of buckling measurements involving the use of enriched uranium rods (1.007% by weight U²³⁵) in light water. The effect of replacing a water reflector with one of uranyl nitrate solution of two different concentrations, 536 and 188 grams of U per liter of solution was investigated for the 0.925" rods with the 1.74 H₂O/U-volume ratio in the core. Some information was also obtained on the extrapolation length to be used in unreflected cases. The application of theory to these lattices, and others, is given in an appendix under separate title, "Buckling Calculations for One Per Cent Enriched Uranium-Water Rod Lattices."
Date: January 16, 1956
Creator: Clayton, E. D. & Neumann, H.
Object Type: Report
System: The UNT Digital Library
Recommended Limit for Radioactive Liquid Disposal From Hanford Separations Plants to Surface Ponds (open access)

Recommended Limit for Radioactive Liquid Disposal From Hanford Separations Plants to Surface Ponds

The purpose of this report is to establish a practical control limit for the activity density (concentration) of radioactive material that may be permitted in large-volume waste waters discharged from the Hanford separations plants to open ponds on the surface of the ground nearby, in consideration of the radiological hazards,
Date: February 16, 1956
Creator: Clukey, H. V.
Object Type: Report
System: The UNT Digital Library
Products Produced in Continuous Neuron Irradiation of Thorium (open access)

Products Produced in Continuous Neuron Irradiation of Thorium

Calculated data and graphs describing the effects of continuous thermal-neutron irradiation of thorium, the usual method of operations of homogeneous reactors, are presented.The buildup and decay of U^233, Pa^233, other heavy isotopes, and fission products are considered on the basis of best available cross-section and fission-yield data. The effects of the heavy isotopes and fission products on neutron economy are discussed.
Date: February 16, 1956
Creator: Gresky, A. T. & Arnold, E. D.
Object Type: Report
System: The UNT Digital Library
Analysis of Thorex Pilot Plant Radiation Exposures During 1955 (open access)

Analysis of Thorex Pilot Plant Radiation Exposures During 1955

The Thorex Pilot Plant at Oak Ridge National Laboratory was operated during 1955, processing reactor-irradiated thorium slugs to recover U233 and thorium and 12 MTR fuel elements to recover U235 and Np237. The radiation exposure received by operating personnel during this period averaged 60 mrcp/man-week. Most radiation exposure was received in areas that were intended to be only slightly or nonradioactive. However, because insufficient decontamination of process solutions was achieved and equipment surfaces became contaminated from equipment failures, these areas became primary sources of personnel exposure. The installation of additional shielding where needed and the prompt removal of surface contamination successfully reduced the radiation levels and exposures in these areas. Remote control of processing equipment and sampling of very radioactive solutions from process equipment was successfully accomplished, and assisted in the reduction of exposure to operating personnel.
Date: November 16, 1956
Creator: McCarley W. T.
Object Type: Report
System: The UNT Digital Library
Effect of Neutron Interaction on Criticality (open access)

Effect of Neutron Interaction on Criticality

A general method is developed to allow calculation of the critical buckling of an assemblage of fissile regions coupled by neutron leakage. Consideration is given both to regions embedded in vacuum and in material media. Several cases of simple geometry are further developed to illustrate the theory.
Date: January 16, 1956
Creator: Stuart, G. W.
Object Type: Report
System: The UNT Digital Library
A Preliminary Study of the Mechanical Properties of M-388, An Aluminum - 1% Nickel Alloy (open access)

A Preliminary Study of the Mechanical Properties of M-388, An Aluminum - 1% Nickel Alloy

M-388 is an aluminum alloy consisting of 2S aluminum with an addition of 1% nickel. Preliminary corrosion studies which were conducted by Dreley and by Dillon indicated that the material exhibited excellent resistance to intergranular type of corrosion in distilled water at temperatures of up to 350 C. The combination of a low thermal neutron cross-section and good corrosion resistance make M-388 alloy a candidate material for use in reactor process tubes and fuel element cans. The purpose of the study was to determine some of the mechanical properties of M-388 aluminum alloy at room temperature and at elevated temperatures.
Date: March 16, 1956
Creator: Johnson, D.E. & Ellis, W.E.
Object Type: Report
System: The UNT Digital Library