IP Library › Granted Patent US 8,532,244
Granted Patent B2
US 8,532,244 · App. 11/762,986 · Granted Sep 10, 2013

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

Inventors: Bruce William Brisson (Galway, NY); William Guy Morris (Rexford, NY); Danian Zheng (Clifton Park, NY); David James Monk (Rexford, NY); Biao Fang (Clifton Park, NY); Cheryl Margaret Surman (Albany, NY); David Deloyd Anderson (Glenville, NY)
Assignee: General Electric Company
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Quick Facts
Patent No.
US 8,532,244
App. No.
11/762,986
Granted
Sep 10, 2013
Kind
B2
Abstract

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.

Claims (11)

1. A probe system for detecting a coolant level and flow velocity in a nuclear reactor, in combination, comprises a conductivity probe; and a time-domain reflectometer probe, wherein the probe system is at least partially arranged in a downcomer of the nuclear reactor.

2. A boiling water reactor, comprising:

a reactor pressure vessel;

a core shroud arranged concentrically inside the reactor pressure vessel to provide an annular downcomer forming a coolant flow path between a wall of the reactor pressure vessel and the core shroud; and

system as recited in claim 1 for determining one of a coolant level and a flow velocity within the reactor.

3. The reactor according to claim 2 , wherein the conductivity probe comprises one of an electrical conductivity (EC) probe and a thermal conductivity (TC) probe.

4. The reactor according to claim 2 , wherein the probe system is at least partially arranged within the downcomer of the reactor for determining the coolant level and the flow velocity within the downcomer of the reactor.

5. The reactor according to claim 2 , wherein the boiling water reactor is a natural circulation boiling water reactor.

6. The probe system according to claim 1 , wherein the conductivity probe comprises one of an electrical conductivity (EC) probe and a thermal conductivity (TC) probe.

7. The probe system according to claim 1 , wherein the nuclear reactor comprises a boiling water nuclear reactor.

8. The probe system according to claim 7 , wherein the boiling water nuclear reactor comprises a natural circulation boiling water reactor.

Assignments (2)
ASSIGNMENT OF ASSIGNOR'S INTEREST Recorded Jan 9, 2009
From: GENERAL ELECTRIC COMPANY
To: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
Reel/Frame 022083/0701 →
ASSIGNMENT OF ASSIGNOR'S INTEREST Recorded Jun 14, 2007
From: BRISSON, BRUCE WILLIAM; MORRIS, WILLIAM GUY; ZHENG, DANIAN; MONK, DAVID JAMES; FANG, BIAO; SURMAN, CHERYL MARGARET; ANDERSON, DAVID DELOYD
To: GENERAL ELECTRIC COMPANY
Reel/Frame 019429/0769 →
Continuity (1)
Related Publication 20080310576A1 · Dec 18, 2008