Texas Attorney General Opinion: C-262 (open access)

Texas Attorney General Opinion: C-262

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, Waggoner Carr, regarding a legal question submitted for clarification: Various questions relating to the operation of the Centrex Telephone System, and other telephone services.
Date: June 2, 1964
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: C-354 (open access)

Texas Attorney General Opinion: C-354

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, Waggoner Carr, regarding a legal question submitted for clarification: Whether, under the stated facts, the Texas State Board of Registration for Professional Engineers has the authority to re-open an application for registration under Section 18 of Article 3271a that was rejected 26 years ago.
Date: December 2, 1964
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
One-group xenon reactivity calculations (open access)

One-group xenon reactivity calculations

A study was initiated in the Pile Physics Unit to evaluate current methods for prediction of xenon behavior in light of newer operating conditions, and thus possibly improve the critical prediction accuracy. Particular areas considered included: (1) validation and limitations of the flux-squared weighting technique for homogenizing localized xenon effects, (ii) effect of elevated graphite temperature on xenon poisoning, (iii) xenon poisoning in the dry lattice, (iv) xenon-control rod interaction and mutual shadowing, and (v) effects of moderate to severe flux distortions. This document comprises the result of that study.
Date: March 2, 1964
Creator: Fredsall, J. R. & Bowers, C. E.
Object Type: Report
System: The UNT Digital Library
Z-Plant weekly report Task 1--2 and recovery operations, January 1, 1964 through December 31, 1964 (open access)

Z-Plant weekly report Task 1--2 and recovery operations, January 1, 1964 through December 31, 1964

None
Date: January 2, 1964
Creator: Walser, R. L. & Lyon, R. Y.
Object Type: Report
System: The UNT Digital Library
Results of thermal-hydraulic experiments with KVNS self-supported fuel in a Zircaloy tube -- K Reactors (open access)

Results of thermal-hydraulic experiments with KVNS self-supported fuel in a Zircaloy tube -- K Reactors

This document presents laboratory data pertaining to the heat-transfer and fluid-flow conditions within a K Reactor process channel using self-supported fuel and a ribless Zircaloy coolant tube. Data are included to show the steady-state hydraulic-demand characteristics during normal conditions and during conditions which simulate a slow flow reduction by plugging upstream of the Panellit pressure tap.
Date: March 2, 1964
Creator: Waters, E. D. & Shockley, M. E.
Object Type: Report
System: The UNT Digital Library
Redox weekly process reports, January--December 1964 (open access)

Redox weekly process reports, January--December 1964

Data compilation.
Date: January 2, 1964
Creator: Isaacson, R. E.
Object Type: Report
System: The UNT Digital Library
Fabrication of enriched hot die sized diffusion bonded fuel elements for Production Test IP-616-A (open access)

Fabrication of enriched hot die sized diffusion bonded fuel elements for Production Test IP-616-A

Hot die sizing (HDS) is a process being investigated to replace the existing AlSi brazing process. Hot die sizing consists of sizing a nickel-plated core and aluminum can assembly with cold dies to produce a diffusion bonded aluminum clad fuel element. Upon completion of fabrication of the first natural uranium hot die sized fuel elements for production test IP-546-A, the next step in evaluation of the process was to assemble enriched fuel for further irradiation testing. This report summarizes the fabrication of 0.947% U-235 enriched fuel elements for ``Production Test IP-616-A.``
Date: October 2, 1964
Creator: Strand, C. A.
Object Type: Report
System: The UNT Digital Library
An Engineering Method for Calculating Protection Afforded by Structures Against Fallout Radiation (open access)

An Engineering Method for Calculating Protection Afforded by Structures Against Fallout Radiation

None
Date: July 2, 1964
Creator: Eisenhauer, C.
Object Type: Report
System: The UNT Digital Library
An Engineering Method for Calculating Protection Afforded by Structures Against Fallout Radiation (open access)

An Engineering Method for Calculating Protection Afforded by Structures Against Fallout Radiation

From Introduction: "The purpose of the paper is to discuss the assumptions and the reasoning by which the calculations described in the Engineering Manual were derived from the data in [1]. The relevant curves from [1] are given in Appendix A and the technical charts from the Engineering Manual are given in appendix B."
Date: July 2, 1964
Creator: Eisenhauer, Charles
Object Type: Report
System: The UNT Digital Library
The Thermal Conductivity of Uranium Monocarbide (open access)

The Thermal Conductivity of Uranium Monocarbide

Uranium carbide shows promise as a fuel material for reactors operating at relatively high temperatures based on its high melting point, high uranium density and high thermal conductivity. Before refined reactor designs can be made, however, good quantitative data on the thermal conductivity at temperatures in excess of 1000C is required. This technical report presents data gathered as part of a continuing study aimed at determining the thermal conductivity of refractory uranium fuels as a function of temperature, density and composition over the temperature range 1000-2200C. At the inception of this program it was felt that an absolute method capable of achieving high temperatures was necessary and that the difficulties encountered in fabricating the large complex specimens needed were justified. The steady state radial heat flow method and apparatus of Rasor and McClelland were therefore chosen. The technical report discusses the experimental equipment and presents results of measurements on three specimens of UC over a temperature range 900 to 1600C. An analysis of the data is made with respect to other physical properties of the material and the measured conductivities are compared with the work of other investigators.
Date: April 2, 1964
Creator: Sobon, J. T.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
Object Type: Report
System: The UNT Digital Library