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SRE Mark II Fuel Handling Machine

Description: Abstract: The Sodium Reactor Experiment Mark II Fuel Handling Machine has been modified to ensure fuel and gas containment during core III operation. A new fuel control system has been designed for the fuel handling machine.
Date: April 20, 1965
Creator: Dietz, H. B.
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
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Study of SCTI Control System

Description: Introduction: This report has been prepared to document the extensive analytical work required to design the control system for the Sodium Components Test Installation (SCTI), constructed for the Atomic Energy Commission at the Atomics International field laboratory.
Date: December 1, 1964
Creator: Griffin, C. W.
Partner: UNT Libraries Government Documents Department
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SNAP 10A FSEM-3 Agena Compatibility Test

Description: From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.
Date: June 15, 1965
Creator: Teresa, M.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
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Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide

Description: Abstract: One hundred gram quantities of uranium dioxide, irradiated to burnup as great as 21,000 Mwd/MTU and previously reprocessed by AIROX (Atomics International Reduction Oxidation), were refabricated into high density pellets and encapsulated for re-irradiation.
Date: December 1, 1964
Creator: Guon, J.; Bodine, J. E. & Sullivan, R. J.
Partner: UNT Libraries Government Documents Department
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The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1

Description: Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date: February 1, 1965
Creator: Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
Partner: UNT Libraries Government Documents Department
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Dynamic Void Fraction Measurement System

Description: Abstract: Various methods and techniques of measuring void fractions in boiling heat transfer media are discussed.
Date: May 15, 1963
Creator: Kendron, J. H.; Stoner, E. E. & Taylor, G. M.
Partner: UNT Libraries Government Documents Department
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The Properties and Irradiation Behavior of U₃Si₂

Description: Abstract: A limited study of the compound U₃Si₂ has been made in reference to its use as a prospective nuclear fuel in sodium cooled reactors.
Date: July 25, 1965
Creator: Shimizu, H.
Partner: UNT Libraries Government Documents Department
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Evaluation of Coolant Impurity Removal Equipment at the OMRE

Description: Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Partner: UNT Libraries Government Documents Department
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Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits

Description: Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date: February 1, 1963
Creator: Holland, J. W.
Partner: UNT Libraries Government Documents Department
open access

KEWB Program Quarterly Progress Report: July-September 1956

Description: From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.
Date: March 1, 1957
Creator: North American Aviation. Atomics International Division. Kinetic Experiments on Water Boilers Program.
Partner: UNT Libraries Government Documents Department
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The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System

Description: Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date: December 31, 1961
Creator: Kramer, D. & Rhodes, C. G.
Partner: UNT Libraries Government Documents Department
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Carbide Fuels in Fast Reactors

Description: Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956

Description: Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date: March 15, 1957
Creator: Trilling, C. A.
Partner: UNT Libraries Government Documents Department
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