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Final Safeguards Summary Report for the Piqua Nuclear Power Facility

Description: 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
Partner: UNT Libraries Government Documents Department
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300,000-KWE SGR Nuclear Power Plant of Current Technology

Description: 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.
Partner: UNT Libraries Government Documents Department
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UC Fuel Element Design and Fabrication

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Boiling Depressurization Transients

Description: 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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
open access

Thermal Stress Testing of Beryllium Oxide Moderator Shapes

Description: 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.
Partner: UNT Libraries Government Documents Department
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Uranium Carbide Transient Heating Experiments - Phase 1

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Neutron Leakage from the 30 Megawatt SGR-P4 Reactor

Description: Abstract: The fast and thermal neutron leakage from the 30 megawatt SGR-P4 reactor has been studied by three independent methods.
Date: August 21, 1953
Creator: Fillmore, F. L.
Partner: UNT Libraries Government Documents Department
open access

High Temperature Liquid Metal Circulating System

Description: 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.
Partner: UNT Libraries Government Documents Department
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Capsule Irradiation of Unalloyed Uranium at High Temperatures

Description: Abstract: Cast and Wrought specimens and restrained wrought specimens of unalloyed uranium were irradiated in the Materials Testing Reactor, as the first in a series of experiments to develop fuel materials for sodium cooled reactors.
Date: August 15, 1962
Creator: Harrington, D. G. & Newton, J. B.
Partner: UNT Libraries Government Documents Department
open access

Boiling Studies for Sodium Reactor Safety: Part 1, Experimental Apparatus and Results of Initial Tests and Analysis

Description: Abstract: An experimental and analytical research program is described which is designed to meet certain specific needs for data and methods required to make improved predictions of transient voids, burnout, flow, and fuel temperature during extreme accidents in sodium-cooled reactors.
Date: August 30, 1963
Creator: Noyes, R. C.
Partner: UNT Libraries Government Documents Department
open access

SRE Heat Transfer System Demolition

Description: From introduction: This report details the extensive modifications to the SRE heat transfer systems required to accomplish increased capacity objectives.
Date: August 31, 1965
Creator: Nicholson, J. O.
Partner: UNT Libraries Government Documents Department
open access

Heat Generation in Thermal Shields

Description: "Heat production resulting from the absorption of gamma ray photons in thermal shields and the leakage of neutrons and photons from ferritic thermal shields are investigated. The gamma rays considered arise from three types of reactor radiation -- thermal neutrons, fast neutrons, and core and reflector gammas. The energy spectra of the fast neutron leakage and absorption have been investigated in some detail because of the significant contribution of fast neutrons to the heating of the concre… more
Date: August 15, 1954
Creator: Heisler, M. & Wetch, J.
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry, Quarterly Progress Report, January-March 1954

Description: "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 fou… more
Date: August 1, 1954
Creator: Motta, E. E.; Bareis, D. W. & Cubicciotti, D.
Partner: UNT Libraries Government Documents Department
open access

Sodium Graphite Reactor, Quarterly Progress Report, December 1953 - February 1954

Description: "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 pre… more
Date: August 1, 1954
Creator: Inman, G. M.
Partner: UNT Libraries Government Documents Department
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Annual Technical Progress Report, AEC Unclassified Programs: 1966

Description: Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1965-66 fiscal year.
Date: August 31, 1966
Creator: North American Aviation. Atomics International Division.
Partner: UNT Libraries Government Documents Department
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