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Consolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins

Description: This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases
Date: July 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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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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Liquid Metal Fuel Reactor Experiment: Quarterly Technical Report No. 1, BAW-1001, July 1, 1956 to November 15, 1956

Description: This is the first quarterly report which summarizes the project work on the Liquid Metal Fuel Reactor Experiment. As the initial contract was not signed until November, 1956, progress within this reporting period has been limited to establishing objectives, determining what research and development will be required, and selecting preliminary design parameters.
Date: 1956-07/1956-11
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: July, 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this months report includes specifications a utility loop, further calculations for fuel rods, drawings were reviewed and specifications for the core reactor were reviewed.
Date: July 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report: Babcock & Wilcox Test Reactor

Description: This preliminary Hazards Summary Report presents to the Atomic Energy Commission (AEC), Division of Licensing and Regulation, a description of the Nuclear Development Center, the characteristics of the proposed site, and an evaluation of the potential hazards associated with operating the test reactor at this location.
Date: July 1962
Creator: Babcock & Wilcox Company
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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