US 11,791,059 B2
System for continually monitoring the condition of nuclear reactor internals
Gregory A. Banyay, Ellwood City, PA (US); Richard A. Basel, Pittsburgh, PA (US); David C. DiBasilio, Pittsburgh, PA (US); Jeremy R. Koether, Beaver Falls, PA (US); Gregory A. Meyer, Bellefonte, PA (US); and Stephen D. Smith, Harmony, PA (US)
Assigned to Westinghouse Electric Company LLC, Cranberry Township, PA (US)
Filed by Westinghouse Electric Company LLC, Cranberry Township, PA (US)
Filed on Feb. 24, 2021, as Appl. No. 17/183,493.
Prior Publication US 2022/0270772 A1, Aug. 25, 2022
Int. Cl. G21C 17/00 (2006.01); G21D 3/00 (2006.01); G21C 9/02 (2006.01); G21C 17/08 (2006.01); G21C 17/10 (2006.01); G21D 3/06 (2006.01)
CPC G21D 3/001 (2013.01) [G21C 17/00 (2013.01); G21C 9/02 (2013.01); G21C 17/08 (2013.01); G21C 17/10 (2013.01); G21D 3/06 (2013.01)] 4 Claims
OG exemplary drawing
 
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.