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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.
Date: July 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Partner: UNT Libraries Government Documents Department
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Control Blade Worth by Partial Water Height and Soluble Boron Methods

Description: The series of experiments described in this paper was performed to determine reactivity values of various patterns of fully inserted cruciform control blades. The experiments yielded the worth of fully inserted blade patterns in terms of their holddown characteristics.
Date: July 1960
Creator: MacKinney, Arland L. & Ball, Russell M.
Partner: UNT Libraries Government Documents Department
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Thermal and Hydraulic Design of the Consolidated Edison Thorium Reactor

Description: This report presents the thermal and hydraulic analyses, both steady state and transient, for the CETR. Methods of calculations are discussed and results of analyses are presented. Steady state analyses are included for: pressure drops, flow distribution, orificing, burnout, fuel central melting, local boiling, and bulk boiling. Transient analyses are performed for several loss of forced coolant flow incidents.
Date: July 1960
Creator: Ferrell, J. K. (James K.); Flora, H. E.; Hostetler, D. R.; Stanek, L. J. & Vannoy, W. M.
Partner: UNT Libraries Government Documents Department
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