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A CANDU-SCWR With a Steam Generator: Preliminary Thermodynamic Assesment and Estimation of Fouling Rates

Posted on:2010-05-18Degree:M.Sc.EType:Thesis
University:University of New Brunswick (Canada)Candidate:Fatoux, WilliamFull Text:PDF
GTID:2442390002974114Subject:Engineering
Abstract/Summary:
The most commonly envisaged configuration of CANDU-SCWR (Super Critical Water Reactor) is a direct cycle which creates the potential for transport of radioactive corrosion products or fission products throughout the entire plant leading to activity fields in the turbines, condenser and feedwater train. A two-loop SCWR is proposed where a steam generator is used to contain the supercritical water coolant and generate steam in a conventional cycle.;To estimate the fouling rate on the tubes of the steam generator, a transport and deposition model was developed. Results indicate a deposition rate approximately 100 times higher than in conventional nuclear reactors. This results in a 4% decrease in efficiency over five years of operation.;The resulting decrease in efficiency and the optimum sizing of the steam generator were obtained from a general thermodynamic model of the plant. Parametric case studies indicate that two once-through IHXs of comparable size to conventional steam generators could be used to achieve an overall plant efficiency of 45%.
Keywords/Search Tags:Steam generator
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