Corrosion of Construction Materials in 234-5 Project Solutions (open access)

Corrosion of Construction Materials in 234-5 Project Solutions

The following report covers the construction materials selected for laboratory corrosion studies and the determination of their corrosion rates in process solutions.
Date: January 31, 1950
Creator: Koenig, W. W.
System: The UNT Digital Library
Fission Product Analysis of Urine (open access)

Fission Product Analysis of Urine

The following report describes a chemical procedure to analyze fission products and long-lived rare earths in both untreated urine samples and the supernates from the precipitation steps in the TTA procedure for plutonium.
Date: May 31, 1950
Creator: Thorburn, R. C.
System: The UNT Digital Library
Development of the Hanford Slave Manipulator for Use in the Multicurie Cells at Hanford (open access)

Development of the Hanford Slave Manipulator for Use in the Multicurie Cells at Hanford

Introduction: "During the early planning of the multicurie cells at Hanford it was decided that a slave type manipulator would be necessary to perform the experiments for which the cells were being designed. The design required steel roofs for installation through a port hole in the face. Technical Services Equipment Development began developing the proposed manipulator in January 1951 by making a study of those existing at that tune. None met the requirements which had been established; therefore, the design of a special manipulator was started immediately."
Date: October 31, 1952
Creator: Field, Richard E. & Gifford, John F.
System: The UNT Digital Library
Strength Properties of Joint Designs for Joining Tubes to Tube Sheets (open access)

Strength Properties of Joint Designs for Joining Tubes to Tube Sheets

This report describes the results of a study to determine the mechanical properties of joining stainless steel tubes to stainless steel tube sheets and evaluating the joint types made by various combinations of rolling and welding.
Date: July 31, 1953
Creator: General Electric Company
System: The UNT Digital Library
Steady State Temperature Distributions in Hollow Slugs (open access)

Steady State Temperature Distributions in Hollow Slugs

This document is a sequel to HW-30226, "Steady State Temperature Distribution in a Solid Slug." A primary feature of the present as well as the former paper is a treatment of the stand heat flow equation in a manner which accounts accurately for the dependence of the thermal conductivity, K, on temperature, v.
Date: December 31, 1953
Creator: Anselone, P. M.; Banks, D. O. & Dean, R. Y.
System: The UNT Digital Library
Correlation of Exponential and PCTR Measurements of Cluster Fuel Elements with Theory (open access)

Correlation of Exponential and PCTR Measurements of Cluster Fuel Elements with Theory

Accurate knowledge of the lattice parameters comprised in the four factor formula k∞=η∈Pi are required for optimum designing of reactors. In the special case of cluster fuel elements conventional handbook formulas are of little use. It is the intent of this paper to report the results of some recent improvements in the calculation of these parameters. By the addition of certain refinements in the calculation of these parameters. By the addition of certain refinements to the conventional calculational methods considerable success has been obtained in the correlation of theory with experiment.
Date: December 31, 1958
Creator: Joanou, G. D.
System: The UNT Digital Library
Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes (open access)

Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date: July 31, 1959
Creator: Knecht, R. L.
System: The UNT Digital Library
PRTR Total Energy Distribution Calculations (open access)

PRTR Total Energy Distribution Calculations

Since the calculation of the PRTR energy distribution was first carried out by J. R. Triplett, the design has become sufficiently fixed to allow a refinement of his values. The present analysis, also, includes a calculation of the fraction of energy which is released in the shroud and process tubers that flows to the primary coolant to the top and bottom shield coolant is taken into consideration. Nuclear data used in the original calculations still appears satisfactory and is, therefore, utilized in the present analysis.
Date: July 31, 1959
Creator: Peterson, R. E.
System: The UNT Digital Library
New Production Reactor Thermal Shielded Studies (open access)

New Production Reactor Thermal Shielded Studies

The relative neutron capture gamma production in several prospective iron thermal shielding materials for the New Production Reactor was measured to determine the merit of adding boron to the metal. It was found that for the beam geometry the used addition of 1 1/2 percent boron to the iron before casting reduced the soft gamma production by a factor of 6.5 and the hard gamma production by a factor of 10. No attempt was made to measure gamma or neutron transmissions.
Date: August 31, 1959
Creator: Friesenhahn, S. J.
System: The UNT Digital Library