用反问题方法重建反应堆中子通量分布,确保结果可靠
On the Well-Posedness of Green's Function Reconstruction via the Kirchhoff-Helmholtz Equation for One-Speed Neutron Diffusion
- 基于基尔霍夫-赫姆霍兹方程构建反演框架
- 证明了从实测数据推导格林函数的解存在唯一性
- 适用于实时监测反应堆中子分布的工程场景
本文提出一种基于外置探测器实时测量数据重构核反应堆中子通量空间分布的方法。基尔霍夫-赫姆霍兹(K-H)方程天然适用于从边界数据估计域内标量场,为该任务提供了合适的数学框架。核心挑战在于获取特定于域结构与中子扩散过程的格林函数。虽然简单几何下存在解析解,但复杂异质域(如核反应堆)需依赖数值方法。本文目标是通过将K-H方程作为反问题求解,证明数据驱动格林函数逼近的适定性。在确立格林函数必须满足的对称性质后,由一速中子扩散模型推导出K-H方程。随后详细描述传感器读数的解读与通量重构算法实现流程。最终,从采样数据推断的格林函数的存在性与唯一性得以证明,保障了所提方法及其预测结果的可靠性。
原文摘要 · Abstract (English)
This work presents a methodology for reconstructing the spatial distribution of the neutron flux in a nuclear reactor, leveraging real-time measurements obtained from ex-core detectors. The Kirchhoff-Helmholtz (K-H) equation inherently defines the problem of estimating a scalar field within a domain based on boundary data, making it a natural mathematical framework for this task. The main challenge lies in deriving the Green's function specific to the domain and the neutron diffusion process. While analytical solutions for Green's functions exist for simplified geometries, their derivation of complex, heterogeneous domains-such as a nuclear reactor-requires a numerical approach. The objective of this work is to demonstrate the well-posedness of the data-driven Green's function approximation by formulating and solving the K-H equation as an inverse problem. After establishing the symmetry properties that the Green's function must satisfy, the K-H equation is derived from the one-speed neutron diffusion model. This is followed by a comprehensive description of the procedure for interpreting sensor readings and implementing the neutron flux reconstruction algorithm. Finally, the existence and uniqueness of the Green's function inferred from the sampled data are demonstrated, ensuring the reliability of the proposed method and its predictions.
Thank you to arXiv for use of its open access interoperability. PaperDance 不是 arXiv 官方产品;中文卡片由大模型生成,请以原文为准。