Steam Cycle Optimization Study for Large Sodium Graphite Nuclear Power Generating Stations (open access)

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
Effect of Carburization on the Low Strain Rate Behavior of Type 304 Stainless Steel: Interim Report (open access)

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
Development, Acceptance and Qualification Testing of the SNAP 10A Ejectable Heat Shield (open access)

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
U-10 Wt % Mo Fuel Element: Irradiation in SRE (open access)

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 (open access)

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
SRE Heat Transfer System Demolition (open access)

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 (open access)

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