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SRE Instrumentation and Control

Description: Introduction: This memo gives a general description of the components and equipment affecting the control of the SRE, and the equipment associated with all reactor services.
Date: May 21, 1956
Creator: Hall, R. J.
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
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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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Piqua Prototype Handling System

Description: Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
Date: May 1960
Creator: Nadler, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System

Description: Abstract: Pressure-temperature isochores were obtained for zirconium-hydrogen alloys, spanning the H/Zr composition range of 1.430 to 1.910. The studies were confined to the temperature limits of 300 to 900ºC, and the pressure limits of 0.01 to 10.0 atm.
Date: May 31, 1964
Creator: Raymond, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Quarterly report with the objectives of evaluating, producing, and maintaining of an up-to-dat set of basic nuclear data; producing and evaluating of multigroup constants; and the improvement of present day methods of neutronic calculations as relates to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safety Evaluation of PNPF Modifications

Description: "The purpose of this report is to examine the safety aspects of PNPF restart on continued operation, after completion of the core cleanup and system modifications."
Date: May 1, 1969
Creator: Huntsinger, M. & Hart, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Pebble-Bed Reactor for Stationary Power Plants

Description: A preliminary study has been made of a solid homogeneous reactor for stationary power plant application. The core consists of graphite spheres impregnated with uranium and thorium, and the coolant is bismuth. This concept possible offers advantages over other solid fuel reactor systems with respect to simplification of core structure, fuel fabrication and fuel handling, and reduction of fuel inventory external to the reactor. From the results of this preliminary study, it appears that the pot… more
Date: May 15, 1954
Creator: Beeley, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Physics, Quarterly Progress Report, November, 1953 - January 1954

Description: "A series of thermal neutron diffusion length measurements has been made on non-multiplying lattice of lead-cadmium alloy rods in D2O. One-inch diameter rods in square lattice spacing of 4, 9, 6, 9, and 12 inches were used. Excellent agreement was found between theoretical and experimental values of the diffusion length. The analysis o the diffusion length measurement required a correction for the epithermal neutrons entering the exponential tank. These epithermal neutrons provided a distri… more
Date: May 15, 1954
Creator: Laubenstein, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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