Reactor internals and core support monitoring system

• US 4,961,898 A
• Filed: 08/30/1988
• Issued: 10/09/1990
• Est. Priority Date: 08/30/1988
• Status: Expired due to Term

• Current Assignee: Westinghouse Electric Company LLC (Brookfield Asset Management Incorporated)
• Original Assignee: Westinghouse Electric Company LLC (Brookfield Asset Management Incorporated)
• Inventors: Singleton, Norman R., Bogard, William T., Bohm, George J., Tgortorice, John A., Palusamy, Sam S., Ciaramitaro, William
• Primary Examiner(s): Wasil, Daniel D.
• Application Number:
  US07/238,051
• Time in Patent Office: 770 Days
• Field of Search: 376/245, 376/249, 376/259, 376/258, 73/579, 73/590
• US Class Current: 376/245
• CPC Class Codes: G21C 17/00 Monitoring; Testing measuring in general G01; Maintaining
• CPC Class Codes: G21D 3/001 Computer implemented control
• CPC Class Codes: Y02E 30/00 Energy generation of nuclear origin
• CPC Class Codes: Y02E 30/30 Nuclear fission reactors
• CPC Class Codes: Y10S 706/915 Power plant

Abstract

A nuclear reactor monitoring system includes incore and excore neutron detectors for producing neutron noise signals and system data including at least one of reactor coolant pump motor current, temperature and pressure of the reactor coolant system and pressurizer pressure and means for diagnosing conditions of the reactor internals and core support structures by comparing analyzed instrumentation signatures. The signatures may be derived from scale model test data, plant test data, analytical model results and trending analysis results. Analyses performed by the system include time and frequency domain analyses of the neutron noise signals and the system data. The analyzed data are compared with rules in a rules base of an expert system to generate a diagnosis of the condition of the reactor internals and core support structures and action recomendations for maintenance of the nuclear reactor.

Claims

1. A method for diagnosing conditions of reactor internals and core support structures in a nuclear reactor, comprising the steps of:

(a) detecting vibration of reactor internals;

(b) receiving signals representing system data including at least two among pressurizer pressure, reactor coolant pump motor current, reactor coolant system pressure, reactor coolant system temperature and reactor coolant system flow rate; and

(c) automatically evaluating the vibration of the reactor internals detected in step (a) based upon all of the signals received in step (b) to diagnose the condition of the reactor internals and core support structures.

2. A method as recited in claim 1,

further comprising the step of (d) automatically evaluating the vibration of the reactor internals based upon structural data including at least one of displacement, acceleration and strain of the core support structures, and

wherein step (c) comprises the steps of:

(ci) analyzing neutron activity emanating from the core of the nuclear reactor using cepstrum analysis to produce an internal vibration indicator;

(cii) analyzing the system data using cepstrum analysis on at least one of the pressurizer pressure, reactor coolant pump motor current, reactor coolant system pressure and displacement, acceleration and strain of the core support structures to produce a system indicator of reactor operation; and

(ciii) comparing the system and internal vibration indicators with rules defining a relationship between structural abnormalities and signatures of the system data and the neutron activity to produce a diagnosis of the condition of the reactor internals and core support structures.

3. A method as recited in claim 2, wherein step (cii) further comprises applying analysis using Duhamel'"'"'s theorem to the temperature of the reactor coolant system in producing the system indicator of reactor operation.

4. A method as recited in claim 1, wherein the signals received in step (b) represent the system data including at least the pressurizer pressure, the reactor coolant pump motor current, the reactor coolant system pressure, the reactor coolant system temperature and the reactor coolant system flow rate.

5. A system for diagnosing conditions of reactor internals and core support structures in a nuclear reactor, comprising:

monitoring means for detecting vibration of reactor internals and for obtaining system data by detecting at least two of pressurizer pressure, reactor coolant pump motor current, reactor coolant system pressure, reactor coolant system temperature and reactor coolant system flow rate; and

diagnosis means for automatically evaluating the vibration of the reactor internals based upon the system data to diagnose the condition of the reactor internals, and the core support structures.

6. A system as recited in claim 5, wherein said monitoring means comprises:

neutron detectors for detecting neutron activity emanating from the core of the nuclear reactor; and

at least two of;

a current detector for detecting the reactor coolant pump motor current;

a temperature detector for detecting the reactor coolant system temperature; and

pressure detectors for detecting the pressurizer pressure and the reactor coolant system pressure.

7. A system for diagnosing conditions of reactor internals and core support structures in a pressurized water nuclear reactor having a reactor vessel and a reactor coolant system with a temperature and pressure maintained by a reactor coolant pump motor, said system comprising:

neutron detectors for outputting a first signal indicative of neutron activity emanating from the core of the nuclear reactor;

a current detector for outputting a second signal indicative of current drawn by the reactor coolant pump motor;

a temperature detector for outputting a third signal indicative of the temperature of the reactor coolant system;

pressure detectors for outputting fourth and fifth signals indicative of pressurizer pressure and the pressure of the reactor coolant system;

signal communication and isolation means for transmitting the first, second, third, fourth and fifth signals; and

a reactor vessel diagnostic unit, connected to said signal communication and isolation means, for analyzing the neutron activity, the temperature, pressure and flow rate of the reactor coolant system, the pressure of the pressurizer and the current of the reactor coolant pump motor and for diagnosing the condition of the reactor internals and core support structures by comparing the results from the analysis with predetermined system data.

8. A system as recited in claim 7, further comprising at least one of:

a flowmeter for outputting a sixth signal indicative of the flow rate of the reactor coolant system;

an accelerometer for measuring motion of at least one of the reactor vessel, reactor vessel internals and a dynamically coupled reactor coolant system component to produce a seventh signal;

a displacement detector for measuring displacement of at least one of the reactor vessel, the reactor vessel internals and the dynamically coupled reactor coolant system component to produce an eighth signal; and

a strain gauge for measuring strain in at least one of the reactor vessel, reactor vessel internals and the dynamically coupled reactor coolant system component to produce a ninth signal, and

wherein said signal communication and isolation means transmits and said reactor vessel diagnostic unit analyzes at least one of the sixth, seventh and eighth signals.

9. A system as recited in claim 8, wherein said reactor vessel diagnostic unit includes means for producing a maintenance scheduling recommendation in dependence upon the condition of the reactor internals and core support structures.

10. A system as recited in claim 8, wherein said signal communication and isolation means transmits and said reactor vessel diagnostic unit analyzes unit analyzes the data represented by all of the first through ninth signals.

11. A method for diagnosing conditions of reactor internals and core support structures in a nuclear reactor having components, comprising the steps of:

(a) receiving sensor data indicating operational states at least two of the components of the nuclear reactor, the sensor data including excore and incore neutron detector noise signals; and

(b) analyzing the sensor data in comparison with scale model test data, full scale plant test data, analytical model results and trending analysis results to diagnose the conditions of the reactor internals and the core support structures.

12. A method as recited in claim 11, wherein step (b) comprises applying expert system rules defined using signal signatures derived from the test data and the analytical model and trending analysis results to identify degradation mechanisms of the reactor internals and the core support structures.