Feed Materials Production Center Summary Technical Report: April 1, 1963-June 30, 1963 (open access)

Feed Materials Production Center Summary Technical Report: April 1, 1963-June 30, 1963

This report summarizes several reports pertaining to uranium processing.
Date: July 18, 1963
Creator: unknown
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1963 - June 1, 1963 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1963 - June 1, 1963

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: July 1, 1963
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
System: The UNT Digital Library
The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results (open access)

The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results

From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date: July 12, 1963
Creator: Zelezny, W. F.
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1963 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: March 1963

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date: July 23, 1963
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle (open access)

An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle

Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).
Date: July 1963
Creator: Vogrin, Joseph A., Jr.
System: The UNT Digital Library
EDP Procedures in Technical Library Operations (open access)

EDP Procedures in Technical Library Operations

Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date: July 30, 1963
Creator: Griffin, Hillis L.
System: The UNT Digital Library
The Hanford Isotopes Production Plant Engineering Study (open access)

The Hanford Isotopes Production Plant Engineering Study

Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Date: July 1963
Creator: La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.
System: The UNT Digital Library
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel (open access)

An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Date: July 1963
Creator: Jackson, C. N., Jr.
System: The UNT Digital Library
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes (open access)

The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date: July 30, 1963
Creator: Pessl, H. J.
System: The UNT Digital Library