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System and method for determining coolant level and flow velocity in a nuclear reactor

United States Patent

September 10, 2013
View the Complete Patent at the US Patent & Trademark Office
A boiling water reactor includes a reactor pressure vessel having a feedwater inlet for the introduction of recycled steam condensate and/or makeup coolant into the vessel, and a steam outlet for the discharge of produced steam for appropriate work. A fuel core is located within a lower area of the pressure vessel. The fuel core is surrounded by a core shroud spaced inward from the wall of the pressure vessel to provide an annular downcomer forming a coolant flow path between the vessel wall and the core shroud. A probe system that includes a combination of conductivity/resistivity probes and/or one or more time-domain reflectometer (TDR) probes is at least partially located within the downcomer. The probe system measures the coolant level and flow velocity within the downcomer.
Brisson; Bruce William (Galway, NY), Morris; William Guy (Rexford, NY), Zheng; Danian (Clifton Park, NY), Monk; David James (Rexford, NY), Fang; Biao (Clifton Park, NY), Surman; Cheryl Margaret (Albany, NY), Anderson; David Deloyd (Glenville, NY)
General Electric Company (Niskayuna, NY)
11/ 762,986
June 14, 2007
STATEMENT REGARDING FEDERALLY SPONSORED RESEARCH & DEVELOPMENT This invention was made with Government support under contract numbers DE-FC07-05ID14635 and DE-FC07-05ID14636 awarded by the Department of Energy. The Government has certain rights in the invention.