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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 8: 1966
The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.
Date:
December 31, 1966
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
Quarterly Technical Progress Report, AEC Unclassified Programs: July-September 1965
Quarterly report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the first quarter of the 1966 fiscal year.
Date:
December 22, 1965
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 1964
Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date:
December 15, 1964
Creator:
Cole, H. S.; Hausknecht, D. F.; Jenkins, O. G., Jr.; Lew, D. E.; Mandel, H.; Pearson, E. N. et al.
System:
The UNT Digital Library
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
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
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
The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System
Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date:
December 31, 1961
Creator:
Kramer, D. & Rhodes, C. G.
System:
The UNT Digital Library
A Device for Continuous Detection of Hydrogen in Sodium
Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date:
December 15, 1960
Creator:
Strahl, H.
System:
The UNT Digital Library
Steady-State Tests of a Reactor Safety Device
Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
Date:
December 15, 1960
Creator:
Springer, T. H.
System:
The UNT Digital Library