Reactor Online Trip Protection via Detector Data Subset Reconstruction
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Solution Overview
Problem
The accuracy of reactor core power distribution calculations is compromised by measurement data errors from neutron detectors, affecting the safety margin of nuclear power operations.
Innovation Solution
A reactor online protection method that involves acquiring multiple detection data sets from self-powered detectors, forming subsets, reconstructing power distribution data, calculating LPD and DNBR values for each subset, and selecting final values to determine reactor trip signals, enhancing reconstruction precision and safety margins.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If measurement data from neutron detectors is used to calculate core power distribution, then the reactor operation monitoring is enabled, but the calculation accuracy is reduced due to measurement data errors
Solution Approach 1:
The patent divides the calculation process into multiple segments by using different combinations of neutron detector data. Instead of relying on a single set of measurement data, the system segments the data into multiple groups (e.g., Group 1, Group 2, Group 3) and performs separate power distribution calculations for each group. This segmentation allows the system to identify and eliminate erroneous measurements by comparing results across different segments, thereby improving calculation accuracy and reliability.
Solution Approach 2:
The patent creates multiple copies of the power distribution calculation by using different combinations of neutron detector data. Each copy represents a separate calculation based on a specific group of detectors. By generating these redundant copies and comparing them, the system can identify outliers and select the most reliable results, effectively copying the calculation process to overcome measurement errors and improve overall accuracy.
2Measurement precision
If multiple detection data sets are used to reconstruct power distribution, then the calculation accuracy is improved, but the computational complexity increases
Solution Approach 1:
The patent segments the multiple detection data sets into distinct groups and processes each group separately through standardized calculation steps. This segmentation approach breaks down the complex task of processing all data simultaneously into manageable segments, where each segment follows the same calculation procedure. This reduces computational complexity by organizing the work into repeatable units while maintaining high accuracy through multiple independent calculations.
Solution Approach 2:
The patent changes the parameters of the calculation system by introducing multiple data groups and their corresponding weight factors. Instead of using fixed detection data, the system dynamically adjusts parameters such as data grouping configurations and weight assignments to optimize calculation accuracy. This parameter flexibility allows the system to adapt to different operational conditions while managing computational complexity through structured parameter management.
Data Source
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AI summary
A reactor online protection method and system, and a readable storage medium. The reactor online protection method comprises: acquiring n groups of detection data corresponding to self-powered detectors; taking m groups of different detection data from among the n groups of detection data, so as to form a subset, and respectively reconstructing reactor core power distribution data of the corresponding subset according to the detection data of each subset; according to the reactor core power distribution data corresponding to each subset, respectively calculating a maximum LPD value and a minimum DNBR value which correspond to the subsets; selecting a final maximum LPD value from among the maximum LPD value corresponding to the subsets, and selecting a final minimum DNBR value from among the minimum DNBR value corresponding to the subsets; and according to the final maximum LPD value and the final minimum DNBR value, a preset LPD setting value and a preset DNBR setting value, determining whether to trigger a reactor trip signal.