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Final Safeguards Summary Report for the Piqua Nuclear Power Facility
Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date:
August 1, 1961
Creator:
unknown
System:
The UNT Digital Library
300,000-KWE SGR Nuclear Power Plant of Current Technology
Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date:
August 1, 1960
Creator:
Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
System:
The UNT Digital Library
UC Fuel Element Design and Fabrication
Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements.
Date:
August 1, 1964
Creator:
Draganchuk, W.
System:
The UNT Digital Library
Boiling Depressurization Transients
Abstract: An analytical and experimental effort toward a better understanding of the mechanisms involved in nuclear power reactor loss-of-pressure accidents is presented.
Date:
August 1, 1964
Creator:
Halfen, F. J. & Berganzoli, F.
System:
The UNT Digital Library
Thermal Stress Testing of Beryllium Oxide Moderator Shapes
Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
Date:
August 1, 1962
Creator:
Sujata, H. L.; King, M. & Waters, F. J.
System:
The UNT Digital Library
Uranium Carbide Transient Heating Experiments - Phase 1
Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec.
Date:
August 1, 1964
Creator:
Stachura, S. J.; Silberberg, M. & Cordy, R. N.
System:
The UNT Digital Library
High Temperature Liquid Metal Circulating System
Introduction: The purpose of this experiment was to demonstrate that a liquid metal heat transfer system could be built and operated at very high temperatures.
Date:
August 1, 1954
Creator:
Keen, R. D.
System:
The UNT Digital Library
The Continuous Neutron Flux Monitor Project: An Interim Report
Abstract: A new concept for continuously monitoring neutron flux has been successfully tested.
Date:
August 1, 1964
Creator:
Smith, Charles R. F. & Springer, Thomas H.
System:
The UNT Digital Library
Separations Chemistry, Quarterly Progress Report, January-March 1954
"Scale-up work on high temperature fuel recovery processes has progressed to the point where the (high temperature) vacuum furnace for several operations to the hot cells has been completed and tested under operating conditions. Small scale experiments on high temperature methods for processing molten irradiated uranium fuel have been made with spent X-10 fuel slug pieces. The results of direct Pu evaporation, treatment with fused fluorides and oxide scavenging were every similar to those found with tracer experiments."
Date:
August 1, 1954
Creator:
Motta, E. E.; Bareis, D. W. & Cubicciotti, D.
System:
The UNT Digital Library
Sodium Graphite Reactor, Quarterly Progress Report, December 1953 - February 1954
"Engineering pertinent to the development of the sodium-cooled, graphite-moderated type of reactor was continued. This included work on problems related to the zirconium canned moderator, low enrichment uranium fuel, sodium piping, secondary coolant system, shielding, and the control and safety elements. A large fraction of the work was devoted specifically to problems of the proposed Sodium Reactor Experiment (SRE) configuration. In this connection, an integrated effort was initiated to prepare a complete preliminary design of the SRE by an early date. In addition, two alternate sodium-graphite reactor configurations were studied. One was an intermediate size, 145 thermal megawatt, unit optimized for the production of low cost plutonium. The second was a low power 10 thermal megawatt intended for power production, but in which sodium circulation through the core was entirely dependent upon thermal convection."
Date:
August 1, 1954
Creator:
Inman, G. M.
System:
The UNT Digital Library