System and method for determining coolant level and flow velocity in a nuclear reactor
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.
- Research Organization:
- GE Global Research, Niskayuna, New York (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- FC07-05ID14636; FC07-05ID14635
- Assignee:
- General Electric Company (Niskayuna, NY)
- Patent Number(s):
- 8,532,244
- Application Number:
- 11/762,986
- OSTI ID:
- 1093234
- Country of Publication:
- United States
- Language:
- English
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