Reactor Core Neutron Flux Decomposition for Transient Accuracy

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Solution Overview

Problem

Conventional methods for determining neutron flux in reactor cores during transient processes suffer from low accuracy due to the varying absorption capacity of control rods, leading to inaccuracies in spatial neutron distribution.

Innovation Solution

A method and apparatus that determine the transient neutron flux by decomposing the neutron flux equation into shape and amplitude functions, using previous moment neutron flux and amplitude values to calculate the current moment neutron flux, enhancing accuracy and rationality without significant computational load.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Device complexity

If the conventional factor splitting method is used to solve the time-dependent neutron transport equation, then the computational complexity is reduced, but the accuracy of neutron flux determination deteriorates under transient conditions

Engineering Contradiction:
Improvecomputational complexityVSAvoidneutron flux accuracy
Core Design Contradiction:
Device complexityVSMeasurement precision

Solution Approach 1:

The neutron flux is segmented into shape function and amplitude function components. The shape function describes the spatial distribution pattern while the amplitude function captures the temporal variation and energy dependence. This segmentation allows the complex transient neutron flux problem to be decomposed into manageable parts that can be solved separately and combined, maintaining accuracy while controlling computational complexity.

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The method transforms the neutron flux from a single complex parameter into multiple parameters (shape function coefficients and amplitude function values). By changing the parameter representation, the method captures transient effects more accurately without proportionally increasing computational burden, as the shape function can be pre-determined or approximated.

Inventive Principle:
Principle #35Parameter changes

2Productivity

If the neutron flux is determined using conventional methods during transient processes, then the calculation speed is maintained, but the accuracy of spatial neutron distribution deteriorates due to varying control rod absorption capacity

Engineering Contradiction:
Improvecalculation speedVSAvoidspatial neutron distribution accuracy
Core Design Contradiction:
ProductivityVSMeasurement precision

Solution Approach 1:

By separating the neutron flux into shape and amplitude functions, the method can use pre-computed or simplified shape functions that capture spatial distribution patterns. This allows rapid calculation of the amplitude function at each time step while maintaining accurate spatial distribution through the shape function, thus preserving both speed and accuracy during transient processes.

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The shape function can be determined in advance or updated less frequently than the full neutron flux solution. This preliminary determination of the spatial distribution pattern allows for faster transient calculations, as only the amplitude function needs to be solved at each time step, significantly reducing computational cost while maintaining spatial accuracy.

Inventive Principle:
Principle #10Preliminary action

Data Source

PatentEP4697362A1Method and apparatus for determining transient neutron fluence rate of core, and device and storage medium
Publication Date: 2026.02.18 CHINA NUCLEAR POWER TECH RES INST CO LTD
  • EP4697362A1 patent drawingFigure 1~3
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  • EP4697362A1 patent drawingFigure 5~6

AI summary

A method and apparatus for determining a transient neutron flux of a reactor core, and a device and a storage medium are provided. The method includes: when a reactor core is in an unsteady state, determining an amplitude value of the reactor core at the previous moment according to a neutron flux of the core at the previous moment (S101); determining a shape value and amplitude value of the reactor core at the current moment according to the amplitude value of the reactor core at the previous moment (S102); and determining a target neutron flux of the reactor core at the current moment according to the shape value and amplitude value of the reactor core at the current moment (S103).