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A Reversing Logarithmic DC Amplifier

Description: Purpose: Automatic recording equipment was designed for use with a high temperature Sykes experiment in which calorimetric measurements were to be made to temperatures approaching 2000* C. At such high temperatures, radiation becomes the dominant mechanism for heat transfer. The temperature differences which are used to determine the magnitude of this transfer no longer are directly proportional to it, but must be related by the Stefan-Boltzman law of radiation.
Date: January 1, 1954
Creator: Carter, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment : Safeguards Summary

Description: Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date: February 1, 1958
Creator: Sletten, H. L. & Blue, L. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OMR Degasifier Loop Experiment

Description: Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date: May 1, 1960
Creator: Corporales, G. W. & Benson, P. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

OMRE Fuel Plate Surface Temperature Measurement

Description: Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date: May 1, 1960
Creator: Sudar, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OMRE Fuel Removal and Shipping Equipment

Description: Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
Date: April 1, 1960
Creator: Mallon, P. J.; Duncan, D. S. & Noyes, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Material Bucklings of Critical and Subcritical Uranium Carbide Fueled Graphite Assemblies: Part 1, Experiment

Description: Introduction: A series of critical and subcritical experiments have been carried out as part of the Advanced Sodium Graphite Reactor (ASGR) Critical Experiments program to provide physics information which would be directly applicable to the AGSR concept.
Date: December 1, 1964
Creator: Hillig, O. R. & Latham, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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