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Transient Flow Performance in a Multi-Loop Nuclear Reactor System

Description: The method present can be used to determine fluid flow and coolant pump speed transients in a nuclear reactor system. Included are transients due to power failure, starting pumps in idle loops, and the opening of an active pump's discharge. Parallel pumps in the system may be analysed independently of each other. Typical cases are presented for the N.S. Savannah (NMSR) and Consolidated Edison Thorium Reactor (CETR).
Date: December 1959
Creator: Boyd, George M., Jr.; Rosser, Ralph M. & Cardwell, Bennett B., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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