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Title: 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.
Authors:
; ; ; ; ; ;
Publication Date:
OSTI Identifier:
1093234
Report Number(s):
8,532,244
11/762,986
DOE Contract Number:
FC07-05ID14636; FC07-05ID14635
Resource Type:
Patent
Research Org:
General Electric Company (Niskayuna, NY)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS