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BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant

Description: An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Mechanism Explaining the Instability of EBR-I, Mark III

Description: Presented at the International Atomic Energy Agencysponsored Seminar on the Physics of Fast and Intermediate Reactors. Vienna, August 3-11, 196l. A feedback model, was developed to account for resonant instabilities in the Mark II core. In this model, the prompt positive power coefficient effect is ascribed to fuel rod bowing and the delayed negative power coefficient effect to thermally lnduced motions in the lower shield plate. Since this model is supported by observations, it is concluded th… more
Date: September 1, 1961
Creator: Smith, R. R.; Matlock, R. G.; McGinnis, F. D.; Novick, M. & Thalgott, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Maritime Reactor Program Annual Progress Report for Period Ending November 30, 1961

Description: Progress is reported on general support of the NS Savannah, operation of the pressurized-water in-pile loop, and advanced core development. A shield survey, iodine adsorption studies, a bioassay development program, preparation of replacement control rod drives, irradiation testing of pressure-vessel steel, a thermal insulation investigation, and an analysis of primary system components for gamm-emitting elements were carried out in the NS Savannah program. Water- chemistry studies in the press… more
Date: March 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis and Optimization of "Full-Length" Diodes

Description: A method of analyzing the axial variation of the heat generation rate, temperature, voltage, current density and emitter heat flux in a thermionic converter is described. The method is particularly useful for the case of "long" diodes, each extending over the full length of the reactor core. For a given diode geometry and fuel distribution, the analysis combines a nuclear solution of the axial fission density profile with the iterative solution of four differential equations representing the th… more
Date: unknown
Creator: Schock, Alfred
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Management in Large Pressurized Water Reactors

Description: Economic and operational ground rules and their effects on fuel management are summarized, and examples showing the approach to typical fuel management problems are presented. The problems associated with in-core fuel management are also discussed, and the merits of various fuel cycling methods are evaluated. (D.C.W.)
Date: October 31, 1964
Creator: Dollard, W. J. & Strawbridge, L. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Pressure Drop, Flow Distribution and Mixing Studies for a Model Heterogeneous Reactor Vessel

Description: A series of hydrodynamic tests was conducted on a 1: 12 scale mcdel of the Yankee reactor vessel and core with four, three, and two loop operation. There was no depression of flow in the center of the core due tc the control rod shrouds or shroud support plate. With four loops operating, flow distribution tests at the core inlet indicated that for all operating conditions the highest velocities occurred in the center region of the core and were a maximum of 18% higher than the average velocitie… more
Date: December 1, 1959
Creator: Berringer, R. T. & Bishop, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRELIMINARY HAZARDS SUMMARY REPORT. PART B. LICENSE APPLICATION

Description: The proposed Yankee Atomic Electric Company Reactor is a pressurized light water reactor plant designed to produce ultimate1y 492 Mw of heat and 134 Mw of net electrical generation at full power. The initial core to be operated in the reactor is designed to produce 392 Mw of heat at full power which provides approximately 110 Mw of net electrical generation. The reactor is fueled with slightly enriched uranium dioxide UO/sub 2/, in the form of pressed and sintered 0.3 in. diameter cylindrical c… more
Date: April 1, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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