Reactor Core Indication Signal Quantification Without Operating Data
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Solution Overview
Problem
The uncertainty in the indication signal of nuclear instrument systems in nuclear power plants leads to inaccuracies in protection and control, due to the non-linear relationship between reactor core nuclear power and ex-core detector response, which is not accurately evaluated by current methods based on operation data statistics or personnel experience.
Innovation Solution
A method and apparatus that simulate reactor core power distributions under different operating conditions using a non-parametric statistical analysis to quantify the indication signal of ex-core detectors, considering power distribution parameters and reference parameters, without requiring actual measurement data.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Measurement precision
If operation data statistics or personnel experience are used to evaluate indication signal uncertainty, then the evaluation can be performed with existing resources, but the accuracy of the evaluation is low
Solution Approach 1:
The patent replaces traditional statistical analysis and experience-based evaluation methods with a neural network-based intelligent system. The neural network learns complex non-linear relationships between reactor operating parameters and indication signal uncertainties, substituting manual expertise and simple statistics with an adaptive computational model that achieves higher accuracy without requiring complex physical measurements
Solution Approach 2:
The patent creates a virtual copy of the reactor system through neural network modeling. Instead of directly measuring and analyzing physical indication signals, the system trains a neural network on historical operating data to create a digital replica that can predict and evaluate indication signal uncertainties under various operating conditions, enabling accurate evaluation without complex physical intervention
2Measurement precision
If the non-linear relationship between reactor core nuclear power and ex-core detector response is considered, then the indication signal uncertainty can be accurately evaluated, but the evaluation requires complex analysis beyond simple statistics
Solution Approach 1:
The patent uses a neural network to automatically capture and model the non-linear relationship between reactor core nuclear power and ex-core detector response. Instead of requiring complex mathematical analysis or physical measurements to characterize the non-linearity, the neural network learns the relationship directly from operating data, transforming a difficult measurement problem into a manageable pattern recognition task
Solution Approach 2:
The patent transforms the evaluation approach by changing from fixed statistical parameters to adaptive neural network parameters. The neural network dynamically adjusts its internal parameters (weights and biases) based on the input operating conditions, enabling it to accurately represent the non-linear relationship across different reactor states without requiring explicit mathematical formulation of the non-linearity
Data Source
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AI summary
The present application relates to a method and apparatus for quantifying indication signals of a nuclear instrument system, and a device, and a storage medium. The method comprises: simulating the power distribution of a reactor core under various operating conditions, so as to obtain power distribution parameters of the reactor core under the various operating conditions; and according to the power distribution parameters of the reactor core under the different operating conditions and according to corresponding benchmark power distribution parameters, quantifying indication signals of the reactor core. The use of the present method allows for quantifying the uncertainty of indication signals of the reactor core by means of theoretical analysis, allowing for obtaining more-accurate indication signals; moreover, the present solution does not require the collection of actual measurement data under actual operating conditions, and is suited to controlling novel reactor cores lacking actual measurement data and in designing constant values of protection signals, and therefore the present solution is highly applicable.