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U-10 Wt % Mo Fuel Element: Irradiation in SRE

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fast Neutron Flux Measurements and Analysis in SM-1 and PM-2A Core and Vessel Mockups

Description: Abstract: This technical report contains a summary of experimental and analytical work performed on cold clean SM-1 Core II with special components and PM-2A Core I each with thermal shield and vessel mockups. The purpose of this work was to define the neutron intensity and spectra to which the pressure vessels are subjected in order to assess the effect of irradiation on the vessel lifetimes. The radial distributions of the energy dependent neutron flux per unit power in the core and vessel m… more
Date: March 31, 1962
Creator: Sontheimer, K. C.; Kemp, S. N.; Lois, L.; Clancy, E. F. & McCool, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 31, 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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