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Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor write by . This book was released on 1961. Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor available in PDF, EPUB and Kindle. A conceptual design and economic evaluation of 300 and 40 MW/.sub e/ steam-cooled fast breeder reactor power plants were performed. A reactor core composed of U-Pu oxide rod-type fuel elements clad with Inconel-X and surrounded by a blanket of depleted UO2 fuel was studied in some detail. Reactor breeding ratios of from 1.27 to 1.5 and overall system doubling times of from 20 to 30 years are achievable. For the near term (1967) 300 MW/sub e/ plant, an energy cost of 7.6 mills/kwh is estimated, based on AEC ground rules for privately financed plants and utilities. This cost may go down to 5.7 mills/kwh by 1975. For the 40 MW/sub e/ plant corresponding energy costs are 19.5 and 13.7 mills/kwh, r -spectively. The R & D program required for this reactor concept is estimated at million with an additional million for improvements leading to the 1975 reactor. Investigation of the operational and safety aspects of the reactor indicated that satisfactory procedures can be used for startup, shutdown, and emergency cooling of the reactor. An increase in reactivity upon flooding can be prevented by incorprating small amounts of high resonance absorption material in the core. Preliminary calculations indicate a substantial increase in reactivity upon loss of coolant for the 300 MW/sub e/ PuO2 fueled reactor. To obtain designs with satisfactory voiding characteristics it may be necessary to provide high neutron leakage as ib a low L/D core or smaller volume core. Acceptable voiding characteristics appear possible with a Pu fueled 40 MWe reactor cooled with H/O steam, a Pu fueled 300MW/sub w/, reactor cooled with D/O steam, and a 300 MW/sub e/ U233-Th fueled 300 MW/sub e/ breeder reactor cooled with H2O steam. (auth).