Final Safeguards Summary Report for the Piqua Nuclear Power Facility (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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
The Continuous Neutron Flux Monitor Project: An Interim Report (open access)

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