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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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Reactor Safety Quarterly Progress Report: May-July 1956

Description: From abstract: Impact tests on the Mark III Hanford safety element indicate that the design is mechanically adequate and does not constitute a personnel hazard.
Date: March 15, 1957
Creator: Miller, N. C.
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment Progress Report: August-October 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 second report of the series, and covers the period from August 1, 1956 through October 31, 1956" (p. 3).
Date: November 15, 1957
Creator: Trilling, C. A.
Partner: UNT Libraries Government Documents Department
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Organic Reactor Waste Gas Analyzer

Description: The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).
Date: October 15, 1958
Creator: Gilroy, H. M. & Edwards, R. J.
Partner: UNT Libraries Government Documents Department
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OMR Control-Safety Rod Component Development Tests

Description: Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date: September 15, 1959
Creator: Howell, J. D.
Partner: UNT Libraries Government Documents Department
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Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Partner: UNT Libraries Government Documents Department
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Terminal Status Report for the Processing Refabrication Experiment

Description: Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
Date: November 15, 1959
Creator: Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
Partner: UNT Libraries Government Documents Department
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Hazards Analysis of the Organic Moderated Reactor Experiment

Description: Introduction: The description of the Organic Moderated Reactor Experiment, (OMRE), its location, its safety system, and operative procedures have been previously detailed. The present report, although dealing with the subject of OMRE safety, has the more detailed intent of (1) determining the behavior of the OMRE under extremely unlikely sets of conditions; and (2) providing additional design information in the areas of reactivity coefficients, burnout heat flux, and reactor control.
Date: December 15, 1959
Creator: Williams, R. O., Jr.; Allen, W. O.; Ash, E. B.; Scott, W. W.; Shimazaki, T. T.; Sletten, H. L. et al.
Partner: UNT Libraries Government Documents Department
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An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
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Thermal Cycling Tests of Porous Uranium

Description: Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date: March 15, 1960
Creator: Wilkinson, L. E.
Partner: UNT Libraries Government Documents Department
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A Multichannel Digital Recording System

Description: Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date: September 15, 1960
Creator: Truitt, R. W.
Partner: UNT Libraries Government Documents Department
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A Device for Continuous Detection of Hydrogen in Sodium

Description: Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date: December 15, 1960
Creator: Strahl, H.
Partner: UNT Libraries Government Documents Department
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Steady-State Tests of a Reactor Safety Device

Description: Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
Date: December 15, 1960
Creator: Springer, T. H.
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
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Investigations of Neutron Penetration in TiH and Steel Slabs

Description: Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date: May 15, 1961
Creator: Karcher, R. H.
Partner: UNT Libraries Government Documents Department
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Metallurgical Aspects of SRE Fuel Element Damage Episode

Description: Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date: October 15, 1961
Creator: Ballif, J. L.
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
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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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