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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Stresses in Bellows

Description: Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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U-10 Wt % Mo Fuel Element: Irradiation in SRE

Description: From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.
Date: August 31, 1965
Creator: Arnold, J. L.; Miller, K. J. & Peterson, R. M.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 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: July 15, 1964
Creator: Auleta, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An Evaluation of the Calder Hall Type of Nuclear Power Plant

Description: Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date: January 18, 1957
Creator: Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)

Description: Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
Date: February 1, 1965
Creator: Botts, W. V.; Marko, M.; McCourt, P. E.; Keshishian, V.; Piccot, A. R. & Budney, G. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SNAP 10A Structural Analysis

Description: Abstract: this report discusses and summarizes all stress analysis done on the SNAP 10A system; it also mentions many of the structural tests which were accomplished.
Date: July 15, 1964
Creator: Boulanger, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices

Description: Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.
Date: June 30, 1963
Creator: Campbell, R. W.; Doyas, R. J.; Field, H. C.; Guderjahn, C. A.; Guenther, R. L.; Hausknecht, D. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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