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7 Matching Results
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Preliminary Safety Analysis of the Sodium-Deuterium Reactor (SDR)
From abstract: This work is a safety analysis of the preliminary design of a nuclear reactor.
Date:
March 6, 1959
Creator:
Beusman, Curtis C. & Bernsohn, E.
System:
The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending December 10, 1951
This quarterly progress report details the ongoing research and experiments at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. The first part of this report discusses reactor theory and design. The second part of this report is not included. The third part of this report discusses materials research. The fourth part of this report includes appendixes
Date:
March 6, 1952
Creator:
Briant, R. C. & Cottrell, W. B.
System:
The UNT Digital Library
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
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
Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962
Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date:
February 6, 1963
Creator:
Oak Ridge National Laboratory. Instrumentation and Controls Division.
System:
The UNT Digital Library
FMPC Solvent Treatment Area - Process Design
This memorandum presents the process design for the solvent reast area of the Feed Materials Production Center. The purpose ofthe transmittal is to provide the basis for the detailed mechanical design and layout of this section of the refinery. Drawings, flowsheets, and specifications are included.
Date:
July 6, 1951
Creator:
Pfeiffer, Carl & Maerker, John B.
System:
The UNT Digital Library
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