Study of SCTI Control System (open access)

Study of SCTI Control System

Introduction: This report has been prepared to document the extensive analytical work required to design the control system for the Sodium Components Test Installation (SCTI), constructed for the Atomic Energy Commission at the Atomics International field laboratory.
Date: December 1, 1964
Creator: Griffin, C. W.
System: The UNT Digital Library
Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide (open access)

Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide

Abstract: One hundred gram quantities of uranium dioxide, irradiated to burnup as great as 21,000 Mwd/MTU and previously reprocessed by AIROX (Atomics International Reduction Oxidation), were refabricated into high density pellets and encapsulated for re-irradiation.
Date: December 1, 1964
Creator: Guon, J.; Bodine, J. E. & Sullivan, R. J.
System: The UNT Digital Library
Material Bucklings of Critical and Subcritical Uranium Carbide Fueled Graphite Assemblies: Part 1, Experiment (open access)

Material Bucklings of Critical and Subcritical Uranium Carbide Fueled Graphite Assemblies: Part 1, Experiment

Introduction: A series of critical and subcritical experiments have been carried out as part of the Advanced Sodium Graphite Reactor (ASGR) Critical Experiments program to provide physics information which would be directly applicable to the AGSR concept.
Date: December 1, 1964
Creator: Hillig, O. R. & Latham, D. W.
System: The UNT Digital Library
Remote Maintenance Techniques for the Processing Refabrication Experiment (open access)

Remote Maintenance Techniques for the Processing Refabrication Experiment

Abstract: This report outlines the general techniques developed for replacement of PRE in-cell equipment or equipment components.
Date: December 1, 1958
Creator: Stoker, Donald J.
System: The UNT Digital Library
Preliminary Test of Natural-Circulation Double-Tube Steam Generator (open access)

Preliminary Test of Natural-Circulation Double-Tube Steam Generator

Abstract: Testing of the Natural Circulation Steam Generator has been conducted with the Sodium Reactor Experiment. A necessary modification of the original feed-water control system was utilized.
Date: December 1, 1959
Creator: Welsh, R. D.
System: The UNT Digital Library