Nuclear Steam Dump Control via Power Mismatch Signals

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Solution Overview

Problem

Nuclear reactors operating at lower reactor coolant average temperatures face reduced steam dump capacity during load rejection transients, leading to potential uncontrollable temperature and pressure increases, which can result in reactor trips, as the existing steam dump control systems rely solely on temperature errors and may not actuate steam dump valves early enough to provide adequate relief.

Innovation Solution

A method that generates a valve control signal by summing temperature error signals based on reactor coolant average temperature deviations and power mismatch errors between nuclear reactor and turbine power, actuating the steam dump system to open valves earlier and more fully during transients, thereby providing rapid steam relief and maintaining reactor operability.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Reliability

If the steam dump control system relies solely on temperature error signals, then the control system remains simple, but the steam dump valves may not actuate early enough during load rejection transients, leading to uncontrollable temperature and pressure increases

Engineering Contradiction:
Improvereactor operability during transientVSAvoidcontrol system complexity
Core Design Contradiction:
ReliabilityVSDevice complexity

Solution Approach 1:

The control system performs preliminary action by detecting power mismatch between the reactor and turbine before temperature significantly rises during load rejection. The power error signal triggers early steam dump valve actuation, preventing the harmful temperature and pressure increases before they occur, rather than waiting for temperature error to develop.

Inventive Principle:
Principle #10Preliminary action

Solution Approach 2:

The power error signal serves as an intermediary indicator that provides earlier warning of transient conditions than temperature signals. By using power mismatch as a leading indicator, the system can trigger preventive steam dumping before the temperature crisis develops, resolving the contradiction between early action and system complexity.

Inventive Principle:
Principle #24Intermediary (Mediator)

2Adaptability or versatility

If the reactor operates at lower reactor coolant average temperatures, then operational flexibility is improved, but steam dump capacity is reduced during load rejection transients

Engineering Contradiction:
Improveoperational flexibilityVSAvoidsteam dump capacity
Core Design Contradiction:
Adaptability or versatilityVSPower

Solution Approach 1:

The control system uses feedback from power mismatch measurements to dynamically adjust steam dump valve actuation. By continuously monitoring the difference between reactor power and turbine power, the system provides early feedback that triggers appropriate steam dumping, compensating for the reduced steam dump capacity inherent in lower temperature operations.

Inventive Principle:
Principle #23Feedback

Solution Approach 2:

The system changes the control parameter from relying solely on temperature error to using power error signal. This parameter change enables the control system to effectively manage steam dump capacity regardless of the operating temperature level, maintaining adequate transient response capability across different operational regimes.

Inventive Principle:
Principle #35Parameter changes

3Reliability

If the steam dump valves are actuated later based only on temperature errors, then valve wear is reduced, but temperature and pressure increases become excessive, potentially causing reactor trips

Engineering Contradiction:
Improveprevention of reactor tripVSAvoidresponse time during transient
Core Design Contradiction:
ReliabilityVSLoss of time

Solution Approach 1:

The system takes preliminary action by detecting and responding to power mismatch before temperature significantly rises. The power error signal triggers steam dump valve actuation in advance, providing rapid response during transients and preventing the development of excessive temperature and pressure conditions that would lead to reactor trips.

Inventive Principle:
Principle #10Preliminary action

Data Source

PatentUS7945011B2Enhanced steam dump (bypass) control system
Publication Date: 2011.05.17 WESTINGHOUSE ELECTRIC CORP
  • US7945011B2 patent drawing
  • US7945011B2 patent drawing
  • US7945011B2 patent drawing

AI summary

The present invention relates to a method of controlling a nuclear reactor during a transient period. The method includes actuating the steam dump system in response to a temperature error signal and a power mismatch signal.