System for continually monitoring the condition of nuclear reactor internals

Patent metadata

Field	Value
Publication number	US-11791059-B2
Application number	US-202117183493-A
Country	US
Kind code	B2
Filing date	Feb 24, 2021
Priority date	Feb 24, 2021
Publication date	Oct 17, 2023
Grant date	Oct 17, 2023

Abstract

A system configured to monitor the structural health of reactor vessel internals of a nuclear reactor is disclosed herein. The system includes a memory configured to store historical information associated with past performance of the nuclear reactor, and an anomaly detection subsystem including a control circuit configured to receive a signal from a sensor. The anomaly detection subsystem is configured to determine, via the control circuit, a characteristic of a vibrational response of the reactor vessel internals based, at least in part, on the signal; access, via the control circuit, the historical information stored in the memory; compare, via the control circuit, the determined characteristic to the historical information stored in the memory; and determine, via the control circuit, a condition of the reactor vessel internals based, at least in part, on the comparison of the determined characteristic and the historical information.

First claim

What is claimed is:

1. A system configured to monitor structural health of reactor vessel internals within a nuclear reactor, the system comprising:
a memory that stores historical information associated with a past performance of the nuclear reactor;
an anomaly detection subsystem comprising a first control circuit configured to receive a signal from a sensor, wherein the signal is associated with a level of neutron noise emitted by the nuclear reactor, and wherein the anomaly detection subsystem is configured to:
determine, via the first control circuit, a characteristic of a vibrational response of the reactor vessel internals based on the received signal;
access, via the first control circuit, the historical information stored in the memory;
compare, via the first control circuit, the determined characteristic to the historical information stored in the memory; and
determine, via the first control circuit, a condition of the reactor vessel internals based on the comparison of the determined characteristic and the historical information; and

a mechanical diagnostic subsystem communicably coupled to the memory and the anomaly detection subsystem, wherein the mechanical diagnostic subsystem comprises a second control circuit, and wherein the mechanical diagnostic subsystem is configured to:
receive, via the second control circuit, the determined condition of the reactor vessel internals from the anomaly detection subsystem;
generate, via the second control circuit, a computer-generated, three-dimensional model of at least a portion of the nuclear reactor; and
generate, via the second control circuit, a diagnostic conclusion associated with the nuclear reactor based on the determined condition of the reactor vessel internals and the computer-generated, three-dimensional model.

2. The system of claim 1 , wherein the anomaly detection subsystem is further configured to generate, via the first control circuit, a digital twin of the nuclear reactor based, at least in part, on the determined condition of the reactor vessel internals, the diagnostic conclusion, and the model.

3. The system of claim 1 , further comprising an asset management platform communicably coupled to the anomaly detection subsystem and the mechanical diagnostic subsystem, wherein the asset management platform is configured to display a prediction associated with a future behavior of the nuclear reactor based, at least in part, on the determined condition of the reactor vessel internals and the diagnostic conclusion associated with the nuclear reactor.

4. The system of claim 3 , wherein the asset management platform is further configured to display an alert, wherein the alert comprises a suggested maintenance plan for the reactor vessel internals based, at least in part, on the determined condition of the reactor vessel internals and the diagnostic conclusion associated with the nuclear reactor.

Assignees

• Westinghouse Electric Co Llc

Inventors

• Banyay Gregory A
• Basel Richard A
• Dibasilio David C
• Koether Jeremy R
• Meyer Gregory A
• Smith Stephen D

Classifications

• G21D3/001 Primary

  Computer implemented control · CPC title

• G21C17/00 Primary

  Monitoring; Testing (measuring in general G01); {Maintaining} · CPC title

• G21C9/02

  Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; {Control elements having arrangements activated in an emergency}(control elements per se G21C7/00) · CPC title

• G21C17/08

  Structural combination of reactor core or moderator structure with viewing means, e.g. with television camera, periscope, window · CPC title

• G21C17/10

  Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain · CPC title