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Quality and availability of fission-products

Description: The information contained in this report was copied from carts used for discussions at Richland on May 4--6, 1965. Representatives of the Martin Company, US Rubber company, General Electric -- HAPO, and AEC-RL00 were present. The data represent the best current information on the quantity, quality, and availability of each fission product considered, i.e., strontium-90, cesium-137, promethium-147, and cerium-144.
Date: December 31, 1965
Creator: Rasmussen, M. J.
Partner: UNT Libraries Government Documents Department
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Criticality Predictions in the Hanford Reactors

Description: The purpose of this study was to examine the general area of criticality prediction errors at the smaller (``pre-K``) reactors. Such errors evolve from a number of uncertainties which are difficult if not impossible to eliminate with present measuring and accounting techniques; the magnitude of these uncertainties in aggregate was indicated in an earlier study about 1.5 milli-k, which, at the time of the study, represented an ``inherent`` prediction error that constituted a practical limit on a… more
Date: March 31, 1965
Creator: Skidmore, S. M. & Bowers, C. E.
Partner: UNT Libraries Government Documents Department
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Monthly record report, Research and Engineering Operation N-Reactor Department

Description: A status report is given for the N Reactor. Brief summaries are included for the following technical activities: Co-product physics studies; Target melting calculations; Critical mass parameters; Stack flooding calculations; Co-product metal handling; Co-producer demonstration test; Thermal hydraulics; Primary cooling system supply characteristics; Fringe tube orificing; Fuel tube power split; Simulated driver-target test; Fuel element failure evaluation; 1.96% Integral-target production test; … more
Date: July 31, 1965
Creator: Leverett, M. C.
Partner: UNT Libraries Government Documents Department
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Decommissioning of the Special Metallurgical Building at Mound Laboratory

Description: The Special Metallurgical Building at Mound Laboratory, a building of 18,515 sq ft of floor space, was decommissioned. This decommissioned facility formerly housed 238PU processes for the fabrication of radioisotopic fueled heat sources. The 238PU work was conducted in 585 linear ft of gloveboxes occupying approximately 12,600 sq ft of the building. All of the gloveboxes, process services, building services, interior walls, and ceilings were removed to the point of exit at the roof. Eighty-five… more
Date: December 31, 1965
Creator: Harris, W. R.; Kokenge, B. R. & Marsh, G. C.
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.
Partner: UNT Libraries Government Documents Department
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The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Description: From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
Date: August 31, 1965
Creator: Hahn, R. D.
Partner: UNT Libraries Government Documents Department
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710 reactor program, progress report No. 13

Description: Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design, (DCC)
Date: March 31, 1965
Partner: UNT Libraries Government Documents Department
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Presentation to the advisory committee on reactor safeguards, September 10, 1965, at Hanford

Description: This document records the chart materials and talk outlines used in presentations at the Advisory Committee on Reactor Safeguards meeting of September 10, 1965, on the Irradiation Processing Department, General Electric Company, operated production reactors. The general objectives of the meeting were to review administration of safety during contractor transition, the status of N-Reactor operation and conversion project progress, and progress on the confinement studies for the production reacto… more
Date: December 31, 1965
Creator: Spink, J.R.
Partner: UNT Libraries Government Documents Department
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