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Reference Design for an OMR-Powered 38,000-DWT Tanker

Description: Abstract: This report presents a reference design of an organic moderated and cooled reactor for the propulsion of a 38,000-dwt tanker.
Date: March 18, 1957
Creator: Gimera, R. J. & Stanbridge, R. E.
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.
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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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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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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Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors

Description: This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.
Date: March 1, 1962
Creator: Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L.
Partner: UNT Libraries Government Documents Department
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Uranium Production Reactor (UPR) Quarterly Progress Report, May-July, 1953

Description: "Measurements of the intra-cell neutron flux distributing for a proposed Uranium Production Reactor have been made using a mock-up of a portion of the reactor core. Thermal neutron and thorium resonance neutron flux-distributions were investigated. As a result of the experimental measurements on the first mock-up, a decrease in thorium content appeared necessary in the reactor design studies. Experiments are now in progress on a second mock-up in which this change has been made."
Date: March 15, 1954
Creator: Laubenstein, R. A.; Houghton, W. J. & Martin, D. H.
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry, Quarterly Progress Report, October-December 1953

Description: "Work has continued on high temperature methods for processing irradiated uranium fuel. Additional results have been obtained with fused halide treatment, solid scavengers and direct Pu distillation. With fussed fluorides about 95 per cent of the Pu was removed from a uranium sample, while treatment of uranium with HC1 gas removed almost all the Pu and many fission products. treatment of molten uranium with uranium oxide removed a substantial fraction of the fission products without removing P… more
Date: March 26, 1954
Creator: Motta, E. E.; Bareis, D. W. & Cubicciotti, D. D.
Partner: UNT Libraries Government Documents Department
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