Reactor Core Power Distribution Uncertainty Using Actual Operating States

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Solution Overview

Problem

Conventional reactor core power distribution measurement systems suffer from significant measurement uncertainty due to the use of hypothetical theoretical parameters, leading to discrepancies between calculated and actual power parameters.

Innovation Solution

A method and apparatus that construct a simulated operating state based on actual reactor core conditions, using precise calculation programs to determine material composition and power distribution, and calculate measurement uncertainty by comparing real and simulated distributions.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Ease of manufacture

If conventional reactor core calculation programs use hypothetical theoretical parameters for sensitivity analysis, then the calculation process is simplified, but the measurement uncertainty becomes unreasonable due to significant differences between assumed and actual parameters

Engineering Contradiction:
Improvecalculation process simplicityVSAvoidmeasurement uncertainty accuracy
Core Design Contradiction:
Ease of manufactureVSMeasurement precision

Solution Approach 1:

The patent changes the parameters from hypothetical theoretical values to actual measured values from the reactor core. The measurement uncertainty analysis device obtains actual power distribution values from detector channels and uses these real parameters instead of theoretical assumptions, thereby resolving the contradiction between calculation simplicity and measurement accuracy.

Inventive Principle:
Principle #35Parameter changes

2Device complexity

If hypothetical theoretical parameters are used in calculation, then the calculation model is easier to establish, but the results show significant difference from actual power parameters

Engineering Contradiction:
Improvecalculation model complexityVSAvoidresult accuracy
Core Design Contradiction:
Device complexityVSReliability

Solution Approach 1:

The patent introduces an intermediary component - the measurement uncertainty analysis device - that bridges the gap between the calculation model and actual reactor conditions. This device obtains actual detector readings and power distribution data from the reactor core, serving as a mediator that translates theoretical calculations into accurate real-world results without complicating the underlying calculation model.

Inventive Principle:
Principle #24Intermediary (Mediator)

3Measurement precision

If actual measurement values from detector channels are used, then the measurement uncertainty accuracy is improved, but the calculation process becomes more complex

Engineering Contradiction:
Improvemeasurement uncertainty accuracyVSAvoidcalculation process complexity
Core Design Contradiction:
Measurement precisionVSDevice complexity

Solution Approach 1:

The measurement uncertainty analysis device performs self-service by automatically obtaining actual measurement values from the detector channels and power distribution data from the reactor core. The system independently processes these real parameters through its analysis modules without requiring external intervention or complex manual calculations, thereby improving accuracy while keeping the process manageable.

Inventive Principle:
Principle #25Self-service

Data Source

PatentEP4730360A1Analysis method and apparatus for measurement uncertainty of power distribution of reactor core, and device
Publication Date: 2026.04.22 CHINA NUCLEAR POWER TECH RES INST CO LTD
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  • EP4730360A1 patent drawingFigure 2
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AI summary

An analysis method and apparatus for measurement uncertainty of a reactor core power distribution, a device, a storage medium and a product are provided. The analysis method and apparatus for measurement uncertainty of a reactor core power distribution includes: constructing a simulated operating state based on an actual operating state of a reactor core, determining state parameters of the reactor core under the simulated operating state, and obtaining a group constant the reactor core (S202); performing a material composition calculation based on a material calculation subroutine in a precise calculation program and the state parameters to obtain a material composition of each fuel rod in the reactor core (S204); performing a power calculation based on a power calculation subroutine in the precise calculation program and the material composition of each fuel rod to obtain a real power distribution of the reactor core, and obtaining a response intensity of a detector in the reactor core (S206); determining power parameters of the reactor core under the simulated operating state based on the state parameters and the group constant, performing a flux map simulation measurement based on the response intensity of the detector and the power parameters to obtain a simulated power distribution of the reactor core (S208); and determining the measurement uncertainty of the reactor core power distribution based on a difference between the real power distribution and the simulated power distribution (S208).