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U-10 Wt % Mo Fuel Element: Irradiation in SRE
From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.
Date:
August 31, 1965
Creator:
Arnold, J. L.; Miller, K. J. & Peterson, R. M.
System:
The UNT Digital Library
The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide
From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
Date:
August 31, 1965
Creator:
Hahn, R. D.
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
SRE Heat Transfer System Demolition
From introduction: This report details the extensive modifications to the SRE heat transfer systems required to accomplish increased capacity objectives.
Date:
August 31, 1965
Creator:
Nicholson, J. O.
System:
The UNT Digital Library
Annual Technical Progress Report, AEC Unclassified Programs: 1966
Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1965-66 fiscal year.
Date:
August 31, 1966
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
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
Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System
Abstract: Pressure-temperature isochores were obtained for zirconium-hydrogen alloys, spanning the H/Zr composition range of 1.430 to 1.910. The studies were confined to the temperature limits of 300 to 900ºC, and the pressure limits of 0.01 to 10.0 atm.
Date:
May 31, 1964
Creator:
Raymond, J. W.
System:
The UNT Digital Library
Steam Cycle Optimization Study for Large Sodium Graphite Nuclear Power Generating Stations
Abstract: This report presents steam cycle optimization studies for large sodium graphite nuclear power generating stations.
Date:
August 31, 1964
Creator:
Schneider, G. A.
System:
The UNT Digital Library
Development, Acceptance and Qualification Testing of the SNAP 10A Ejectable Heat Shield
From abstract: The development, acceptance, and qualification tests performed on the SNAP-10A Ejectable Heat Shield and components, the results of those tests, and the conclusions drawn from the results are presented in this report.
Date:
August 31, 1965
Creator:
Sperow, H. L.
System:
The UNT Digital Library
Effect of Carburization on the Low Strain Rate Behavior of Type 304 Stainless Steel: Interim Report
Abstract: Pressure stress-rupture specimens of thin walled Type 304 stainless steel tubing have been tested at temperatures to 1300°F in the presence of an internal diffusion limited carbon source.
Date:
August 31, 1965
Creator:
Stone, D. H. & Schwartz, A. D.
System:
The UNT Digital Library