Title :
Steam-generator instrumentation for a nuclear power plant with analog computer verification of dynamic action
Author :
Lynch, E. E. ; Waite, D. P.
Author_Institution :
General Electric Company, Lynn, Mass.
Abstract :
High-performance nuclear reactor designs of the pressurized-water type are used with smaller than conventional steam drums to convert from primary coolant heat to steam in a heat exchanger. ¿Swell¿ caused by steam bubbles changing in size and raising the liquid level various amounts at different steam-generation levels poses an acute feed water control problem.
Keywords :
Coolants; Inductors; Instruments; Liquids; Power generation; Transmitters; Valves;
Journal_Title :
American Institute of Electrical Engineers, Part I: Communication and Electronics, Transactions of the
DOI :
10.1109/TCE.1958.6372708
