Invention Grant
US08532244B2 System and method for determining coolant level and flow velocity in a nuclear reactor
有权
用于确定核反应堆中的冷却剂水平和流速的系统和方法
- Patent Title: System and method for determining coolant level and flow velocity in a nuclear reactor
- Patent Title (中): 用于确定核反应堆中的冷却剂水平和流速的系统和方法
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Application No.: US11762986Application Date: 2007-06-14
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Publication No.: US08532244B2Publication Date: 2013-09-10
- Inventor: Bruce William Brisson , William Guy Morris , Danian Zheng , David James Monk , Biao Fang , Cheryl Margaret Surman , David Deloyd Anderson
- Applicant: Bruce William Brisson , William Guy Morris , Danian Zheng , David James Monk , Biao Fang , Cheryl Margaret Surman , David Deloyd Anderson
- Applicant Address: US NY Niskayuna
- Assignee: General Electric Company
- Current Assignee: General Electric Company
- Current Assignee Address: US NY Niskayuna
- Agent Ann M. Agosti
- Main IPC: G21C17/00
- IPC: G21C17/00

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.
Public/Granted literature
- US20080310576A1 SYSTEM AND METHOD FOR DETERMINING COOLANT LEVEL AND FLOW VELOCITY IN A NUCLEAR REACTOR Public/Granted day:2008-12-18
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