Summary Report of Physics Measurements on SM-1 Core I (open access)

Summary Report of Physics Measurements on SM-1 Core I

Abstract: This technical report summarizes all core physics experiments performed on SM-1 Core I and SM-2 Rearranged and Spiked Core I throughout core life. These measurements were obtained on site during the 16.4 MWYR lifetime of SM-1 Core I and 1.6 MWYR lifetime of SM-1 Rearranged and Spiked Core I. SM-1 Core I was the first stainless steel - UO2 dispersion core to burn out in the Army Nuclear Power Program. Experimental techniques are described and a complete history of fuel movements in the core presented. Measurements include control rod bank positions during all core conditions, temperature and pressure coefficients, control rod calibrations, transient poison effects, source multiplication, and stuck rod positions. The effect of core rearrangement and spiking on core reactivity and core life is also reported. Applicable measurements from the SM-1 zero power experiments are included.
Date: February 6, 1962
Creator: Weiss, S. H.
System: The UNT Digital Library
SM-2 Final Design Progress Review Report: December 16, 1959 to March 1, 1960 (open access)

SM-2 Final Design Progress Review Report: December 16, 1959 to March 1, 1960

From introduction: "The contract covers final design of the SM-2 Nuclear Power (PWR) Steam Electric Station, described in the preliminary design report, APAE 40, Volumes I and II."
Date: April 6, 1960
Creator: Knighton, G. W.
System: The UNT Digital Library
Pressure Intensification Provided by External Pressure on a Cylinder Composed of Four Anvils (open access)

Pressure Intensification Provided by External Pressure on a Cylinder Composed of Four Anvils

Results of experimental investigation for improving intensification and to reduce stress concentrations for anvil redesign.
Date: December 6, 1963
Creator: Huddleston, R. L.
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: December 1961

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date: April 6, 1962
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Subcritical and Critical Flow Through Straight-Through, Elbow, and Tee "AN" Fittings and Sharp-Edged Orifices at Elevated Temperatures (open access)

Subcritical and Critical Flow Through Straight-Through, Elbow, and Tee "AN" Fittings and Sharp-Edged Orifices at Elevated Temperatures

Investigation of the flow through straight-through , elbow, and tee "AN" fittings at negligible approach velocity with approach temperatures up to 1100 degrees F.
Date: March 6, 1957
Creator: Ducoffe, Arnold L.; Bennett, John R. & Ray, C. Gable
System: The UNT Digital Library
The Crystal Structure of Uranium Tetrafluoride (open access)

The Crystal Structure of Uranium Tetrafluoride

Fourier refinement analysis of the uranium parameters in uranium tetrafluoride.
Date: June 6, 1951
Creator: Burbank, R. D.
System: The UNT Digital Library