Annals of Nuclear Energy最新文献_第5页

Fuzzy variable-parameter output feedback control method based on axial spatial distribution parameter model of nuclear reactor power 基于核反应堆功率轴向空间分布参数模型的模糊变参数输出反馈控制方法

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-02-05 DOI: 10.1016/j.anucene.2026.112181

Airan Dang, Bowen Tu, Xiuchun Luan

Both the time variation and spatial distribution of nuclear reactor power are research objects in the field of nuclear reactor control. For the time variation of power, the control objective is to align the actual power change with the desired power change, namely achieving load following. For the spatial distribution of power, the control objective is to prevent overshoot when the axial peak power moves. Meeting both objectives is crucial for the safe operation of nuclear reactors. Therefore, the distributed parameter model is established in this paper based on the neutron diffusion equation to meet this requirement, as it is capable of simultaneously observing both power variation and axial spatial power distribution. Typically, two control objectives require two actuators, forming a dual-input dual-output (DIDO) system. However, the coupling between the two control rods complicates controller design significantly. Simulations of the movement of a single group of control rods have shown that it also influences both power time variation and spatial distribution. Thus, this paper designs a fuzzy variable-parameter output feedback controller for a single group of control rods, and simulation results verify the feasibility of this method. Compared with the DIDO system, the single-group control rod approach, while slightly inferior in performance, offers a substantial reduction in complexity.

核反应堆功率的时间变化和空间分布都是核反应堆控制领域的研究对象。对于功率的时间变化，控制目标是使实际功率变化与期望功率变化一致，即实现负载跟随。对于功率的空间分布，控制目标是防止轴向峰值功率移动时的超调。实现这两个目标对于核反应堆的安全运行至关重要。因此，为了满足这一要求，本文基于中子扩散方程建立了分布式参数模型，该模型能够同时观测功率变化和轴向空间功率分布。通常，两个控制目标需要两个执行器，形成双输入双输出（DIDO）系统。然而，两个控制棒之间的耦合使控制器设计变得非常复杂。对单组控制棒运动的仿真表明，它还会影响功率的时间变化和空间分布。因此，本文针对单组控制棒设计了模糊变参数输出反馈控制器，仿真结果验证了该方法的可行性。与DIDO系统相比，单组控制棒方法虽然性能稍差，但大大降低了复杂性。

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引用次数: 0

Sealing behavior of bolted flange system with double metallic C-rings during prolonged high-temperature operation 双金属c形环螺栓法兰系统在长时间高温工况下的密封性能

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-02-06 DOI: 10.1016/j.anucene.2026.112182

Yijun Chai , Yunzhou Wu , Wenhao Yu , Qin Ma , Xiongwei Yang , Yueming Li

Bolted flange joint, serving as a primary pressure barrier in nuclear reactors, is essential to operational safety. Double metallic C-ring shows potentials for next Generation reactors, while its sealing performance during prolonged high-temperature operation remains inadequately characterized. To this end, a numerical methodology incorporating essential factors such as bolt preload, high-temperature creep behavior, structural contact, and multi-physical coupling, is developed. The fundamental material creep behavior is characterized through high-temperature stress relaxation experiments. The investigation emphasizes evolutionary characteristics of contact stress and rebound behavior of the double C-rings across loading stages, while a higher bolt preload does not always improve sealing performance; conversely, its synergistic effect with internal medium pressure can lead to complete failure of the inner seal. Therefore, the inner ring experiences more significant rebound, indicating vulnerability for sealing failure. Additionally, the correlations among bolt preload, linear load, and rebound magnitude are quantitatively described. Results show that throughout long-term stress relaxation service, relaxation of both the linear load and bolt preload occurs predominantly within the first 120 h, at a rate below 5%, and stabilizes thereafter. This demonstrates that the bolted flange system can maintain a high preload level even after prolonged high-temperature service under the current operating conditions. The proposed framework could be critically useful in assessing the sealing status and the effective sealing duration of the flange system.

螺栓连接法兰作为核反应堆的主要压力屏障，对核反应堆的运行安全至关重要。双金属c环在下一代反应堆中具有发展潜力，但其在长时间高温工况下的密封性能仍有待进一步研究。为此，开发了一种结合螺栓预紧力、高温蠕变行为、结构接触和多物理耦合等基本因素的数值方法。通过高温应力松弛实验表征了基本材料的蠕变行为。研究强调了双c形环在加载阶段的接触应力和回弹行为的演化特征，而较高的螺栓预紧力并不总是能提高密封性能；反之，其与内介质压力的协同作用会导致内密封完全失效。因此，内环回弹更明显，表明密封失效的脆弱性。此外，定量描述了锚杆预紧力、线性载荷和回弹幅度之间的关系。结果表明：在长期应力松弛过程中，线性载荷和锚杆预紧力的松弛主要发生在前120h，松弛率低于5%，之后趋于稳定；这表明，在目前的操作条件下，即使在长时间高温工作后，螺栓法兰系统也可以保持高预紧力水平。所提出的框架在评估法兰系统的密封状态和有效密封持续时间方面非常有用。

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引用次数: 0

Robust and fault-tolerant control of MSBR reactor using a hybrid QFT–PID–LSTM framework with disk margin analysis 基于QFT-PID-LSTM混合框架和磁盘裕度分析的MSBR反应器鲁棒容错控制

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-01-10 DOI: 10.1016/j.anucene.2026.112131

Achu Govind K.R.

Reliable reactive power regulation in Molten Salt Breeder Reactor (MSBR) cores is essential for safety and efficiency. Conventional controllers often exhibit poor robustness and fault tolerance under uncertainties, nonlinear dynamics, and disturbances. To address these limitations, this work introduces a Quantitative Feedback Theory (QFT)-based proportional integral derivative (PID) controller enhanced with Long Short-Term Memory (LSTM) modeling. The controller is designed in two stages. First, a QFT-based PID controller is synthesized to guarantee stability and robust performance across plant uncertainty sets. Robustness, disturbance rejection, and tracking are enforced as frequency-domain inequalities. In the second stage, an LSTM network is integrated to adaptively tune PID gains in real time. This ensures that predictions inherently satisfy robust stability, tracking, and disturbance rejection constraints. A composite performance-driven loss further biases the network toward minimizing integral absolute error (IAE), overshoot, and settling time while preserving robustness. The QFT-PID-LSTM controller achieved faster rise time, shorter settling time, negligible steady-state error, and lower control effort compared to existing approaches. Quantitative indices showed reductions of nearly 90% in performance metrics and 80% in statistical measures. Disk margin analysis confirmed stability, while Monte Carlo simulations demonstrated tightly bounded error distributions. The controller also maintained stability and accurate tracking under both sensor and actuator faults, confirming strong robustness and fault tolerance.

熔盐增殖反应堆（MSBR）堆芯可靠的无功功率调节对安全性和效率至关重要。传统的控制器在不确定性、非线性动力学和干扰下往往表现出较差的鲁棒性和容错性。为了解决这些限制，本工作引入了一种基于定量反馈理论（QFT）的比例积分导数（PID）控制器，增强了长短期记忆（LSTM）建模。控制器的设计分为两个阶段。首先，合成了一种基于qft的PID控制器，以保证整个系统的稳定性和鲁棒性。鲁棒性、抗干扰性和跟踪性作为频域不等式被强制执行。第二阶段，集成LSTM网络，实时自适应调整PID增益。这确保了预测本质上满足鲁棒稳定性、跟踪和干扰抑制约束。复合性能驱动的损失进一步使网络倾向于在保持鲁棒性的同时最小化积分绝对误差（IAE）、超调和稳定时间。与现有方法相比，QFT-PID-LSTM控制器实现了更快的上升时间、更短的沉降时间、可忽略的稳态误差和更低的控制工作量。定量指标显示，性能指标减少了近90%，统计指标减少了80%。磁盘裕度分析证实了稳定性，而蒙特卡罗模拟显示了紧密有界的误差分布。该控制器在传感器和执行器故障下均保持稳定和准确跟踪，具有较强的鲁棒性和容错性。

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引用次数: 0

Transient multiphysics simulations with pin power reconstruction in the Griffin reactor physics code Griffin反应堆物理代码中pin功率重建的瞬态多物理场模拟

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-01-09 DOI: 10.1016/j.anucene.2025.112111

Shikhar Kumar , Changho Lee , Vincent Laboure , Yeon Sang Jung , Stefano Terlizzi , Yaqi Wang , Javier Ortensi

This work introduces the pin power reconstruction capability available in the Griffin reactor physics code. This capability is implemented in an unstructured mesh framework, and the methods introduced are applied to the 2D SIMBA reactor core, which has assemblies and pins arranged in a hexagonal lattice. Since this reactor has a non-Cartesian geometry and also operates in the thermal spectrum, a general approach to pin power reconstruction is adopted, where SPH-based equivalence is leveraged to preserve assembly-wise reaction rates, while computing full-core form functions to preserve pin-wise fission production rates within the fuel pins of the reactor core. In a 2D microreactor benchmark problem, this pin power reconstruction approach was shown to reproduce pin powers compared to the Serpent2 Monte Carlo code for fixed temperature conditions and control drum rotation angles, yielding a core-wide RMS error level of 0.6% and a maximum absolute pin error of 2.3%. In addition, a tabulated library of multigroup cross sections, SPH factors, and form functions was generated to demonstrate the applicability of pin power reconstruction to a thermal feedback problem. Finally, a control drum transient was successfully simulated, showcasing the application of pin power reconstruction in a transient multiphysics feedback problem.

本文介绍了Griffin反应堆物理代码中可用的引脚功率重构能力。该功能在非结构化网格框架中实现，并将所介绍的方法应用于二维SIMBA反应堆堆芯，该堆芯的组件和引脚排列在六边形晶格中。由于该反应堆具有非笛卡尔几何形状，并且也在热谱中运行，因此采用了一种通用的针功率重建方法，其中利用基于sph的等效来保持装配方向的反应速率，同时计算全芯形式函数以保持反应堆堆芯燃料针内针方向的裂变产生速率。在一个二维微反应器基准问题中，与Serpent2蒙特卡罗代码相比，该引脚功率重建方法在固定温度条件和控制转鼓旋转角度下再现了引脚功率，产生了0.6%的核心范围的均方根误差水平，最大绝对引脚误差为2.3%。此外，还生成了多组截面、SPH因子和形式函数的表格库，以证明引脚功率重构对热反馈问题的适用性。最后，对一个暂态控制鼓进行了成功的仿真，展示了引脚功率重构在瞬态多物理场反馈问题中的应用。

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引用次数: 0

Pin-resolved ex-core detector response function methodology based on the 2D/1D high-fidelity adjoint neutron transport calculation 基于二维/一维高保真伴随中子输运计算的引脚分辨力前核探测器响应函数方法

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-01-27 DOI: 10.1016/j.anucene.2026.112169

Zhinan Xie , Chen Hao , Wen Yin

Accurate calculation of the detector response function is critical in power reconstruction using ex-core detectors. The Monte Carlo and 3D discrete ordinates methods have been applied to calculate the ex-core detectors response function. However, since ex-core detectors are located far from the reactor core, the large neutron flux gradients between the core and the ex-core detector, as well as the weak contribution of in-core neutrons to the detector response, lead to significant limitations of the computational efficiency and accuracy for the Monte Carlo method. And for 3D discrete ordinates method, the resolution of the detector response function is limited due to the homogenization approximations. Therefore, achieving efficient and accurate whole-core, pin-resolved detector response function calculations remain a significant challenge. To address the challenges of computational efficiency and resolution inherent in conventional methods, the 2D Method of Characteristics / 1D Nodal Expansion Method coupling method with multi-group coarse mesh finite difference method acceleration is used to carry out high-fidelity adjoint transport calculations, enabling direct pin-resolved detector response function calculation. Numerical verification is performed using the 2D EPRI-9 model, the 3D C5G7 model and the low temperature heating reactor. The results demonstrate that the 2D/1D method can accurately and efficiently compute pin-resolved detector response function, achieving well agreement with Monte Carlo results.

探测器响应函数的精确计算是利用脱芯探测器进行功率重构的关键。采用蒙特卡罗法和三维离散坐标法计算了前核探测器的响应函数。然而，由于前堆芯探测器距离反应堆堆芯较远，堆芯与前堆芯探测器之间的中子通量梯度较大，以及堆芯中子对探测器响应的贡献较小，导致蒙特卡罗方法的计算效率和精度受到很大限制。而对于三维离散坐标法，由于均匀化近似，探测器响应函数的分辨率受到限制。因此，实现高效、准确的全核、引脚解析检测器响应函数计算仍然是一个重大挑战。为了解决传统方法固有的计算效率和分辨率问题，采用二维特征法/一维节点展开法耦合多组粗网格有限差分法加速进行高保真伴随输运计算，实现直接针分辨探测器响应函数计算。采用二维EPRI-9模型、三维C5G7模型和低温加热反应器进行数值验证。结果表明，二维/一维方法可以准确、高效地计算引脚分辨探测器响应函数，与蒙特卡罗结果吻合较好。

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引用次数: 0

Demonstrating the Osier framework for energy system and nuclear fuel cycle optimization 展示了能源系统和核燃料循环优化的Osier框架

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-01-23 DOI: 10.1016/j.anucene.2026.112151

Samuel Gant Dotson , Madicken Munk , Kathryn Dorsey Huff

Energy system optimization models are a class of tools designed to optimize energy planning and are used by energy planners and decision-makers to generate insights that inform energy policy. However, existing tools are challenged by real-world scenarios which require optimization across multiple objectives. In this paper, the multi-objective energy system optimization framework, Osier, is demonstrated. Osier leverages genetic algorithms to calculate a set of co-optimal solutions called a Pareto front. Osier also introduces a novel algorithm to identify a subset of maximally different solutions within the sub-optimal space to address structural uncertainty related to unmodeled objectives. By producing multiple solutions, Osier gives modelers and decision-makers the tools to meaningfully engage with public stakeholders and learn their preferences, thereby attending to issues of procedural and recognition justice. This work verifies Osier’s suitability for energy modeling problems with two in silico experiments. The first set of experiments compare Osier to a more mature energy system optimization model, Temoa, to verify that Osier produces results consistent with known methods. The results for a least-cost optimization with Osier and Temoa show strong agreement, within 0.5% of each other. In the second, Osier reanalyzes a set of nuclear fuel cycle options from the SET tool through the lens of Pareto optimality.

能源系统优化模型是一类旨在优化能源规划的工具，被能源规划者和决策者用来产生为能源政策提供信息的见解。然而，现有的工具受到需要跨多个目标进行优化的现实场景的挑战。本文对多目标能源系统优化框架Osier进行了论证。Osier利用遗传算法来计算一组称为帕累托前沿的共同最优解。Osier还引入了一种新的算法来识别次最优空间中最大不同解的子集，以解决与未建模目标相关的结构不确定性。通过提供多种解决方案，Osier为建模者和决策者提供了有意义地与公众利益相关者接触并了解他们偏好的工具，从而解决程序和认可正义的问题。本文通过两个计算机实验验证了Osier对能量建模问题的适用性。第一组实验将Osier与更成熟的能源系统优化模型Temoa进行比较，验证Osier的结果与已知方法一致。Osier和Temoa的最小成本优化结果显示出很强的一致性，误差在0.5%以内。在第二部分中，Osier通过帕累托最优的视角重新分析了set工具中的一组核燃料循环选项。

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引用次数: 0

Dissolved oxygen concentration control and prediction modelling for liquid LBE loop: UPBEAT loop 液体LBE回路溶解氧浓度控制与预测建模：乐观回路

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-01-18 DOI: 10.1016/j.anucene.2026.112140

Ruixian Liang, Wei Mao, Xiangtian Hou, Zulong Hao, Haicai Lyu, Hao Wu, Huiping Zhu, Fang Liu, Yang Liu, Fenglei Niu

The application of liquid lead–bismuth eutectic (LBE) alloy coolant technology necessitates the implementation of real-time monitoring of dissolved oxygen concentration. Furthermore, in accordance with operational requirements, the dissolved oxygen concentration within the liquid LBE must be maintained within a reasonable target range. In order to enhance the provision of rapid and efficient oxygen replenishment to the liquid LBE loop, the oxygen supply behavior of the mass exchanger (MX) was modelled. The development of the oxygen control model of the MX was achieved by the collection of input (MX temperature) and output (signal of oxygen sensor) data from the solid-phase oxygen control experiments in the liquid LBE recirculation loop. The least squares method and neural network algorithm were utilised in the development of the oxygen control model, respectively. The findings demonstrate the efficacy of the oxygen control model in predicting the dissolved oxygen concentration within the LBE loop. This provides a theoretical framework for the subsequent optimisation of the solid-phase oxygen control strategy within the LBE system.

液态铅铋共晶（LBE）合金冷却剂技术的应用要求对溶解氧浓度进行实时监测。此外，根据操作要求，液态LBE内溶解氧浓度必须保持在合理的目标范围内。为了提高液相LBE循环的快速高效补氧能力，对质量交换器（MX）的供氧行为进行了建模。通过收集液体LBE循环回路固相氧控制实验的输入（MX温度）和输出（氧传感器信号）数据，实现了MX氧控制模型的建立。利用最小二乘法和神经网络算法分别建立了氧控制模型。研究结果证明了氧控制模型在预测LBE环内溶解氧浓度方面的有效性。这为LBE系统内固相氧控制策略的后续优化提供了理论框架。

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引用次数: 0

Development and improvement of the quadratic depletion method 二次耗竭法的发展与改进

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-02-01 DOI: 10.1016/j.anucene.2026.112179

Runze Liu, Zhouyu Liu, Xiaoqing Liang, Liangzhi Cao, Hongchun Wu

In nuclear reactor depletion calculations, the conventional predictor–corrector (PC) method requires two neutron transport calculations per burnup step. However, in high-fidelity calculations, these two transport calculations significantly reduce computational efficiency, especially for reactors reloaded with gadolinium (Gd)-bearing fuels, which require much finer depletion steps. The quadratic depletion (QD) method skips the corrector-step transport calculation and employs quadratic interpolation combined with a post-correction method to preserve accuracy. Nevertheless, the traditional QD method requires an excessive number of substeps to maintain precision for Gd-bearing systems, leading to high computational costs. To address this issue, a novel two-level predictor–corrector QD (TL-PC-QD) method is proposed to reduce the number of substeps. Comparative applications to Gd-bearing assembly and whole-core cases show that the TL-PC-QD method significantly reduces the number of substeps of the traditional QD method.

在核反应堆耗尽计算中，传统的预测校正（PC）方法需要在每个燃耗步骤中进行两次中子输运计算。然而，在高保真度计算中，这两种输运计算显著降低了计算效率，特别是对于重新加载含钆（Gd）燃料的反应堆，这需要更精细的耗尽步骤。二次耗损法（QD）跳过了校正阶跃输运计算，采用二次插值与后校正相结合的方法来保持精度。然而，传统的QD方法需要过多的子步骤来保持gd轴承系统的精度，导致计算成本高。为了解决这一问题，提出了一种新的两级预测校正QD （TL-PC-QD）方法，以减少子步数。在gd轴承装配和全芯情况下的对比应用表明，TL-PC-QD方法显著减少了传统QD方法的子步骤数量。

引用次数: 0

Appropriate selection of objective functions with constraints for successive multicycle optimization of the HPR1000 reactor core using deep learning enhanced multi-objective genetic algorithm 基于深度学习增强型多目标遗传算法的HPR1000堆芯连续多周期优化目标函数的选择

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-02-04 DOI: 10.1016/j.anucene.2026.112128

Muhammad Kamran Butt , Samia Nasir , Muhammad Ahmad , Muhammad Talha Bin Humayun , Ahmer Riaz , Chenghui Wan , Liangzhi Cao

Once the core exits from the equilibrium reloading scheme, the nuclear core designer needs to perform multicycle fuel reloading pattern optimization (MCO). MCO can be performed either as successive multicycle optimization, also known as cycle-by-cycle optimization, or simultaneous multicycle optimization, wherein a set of cycles is optimized simultaneously. In this research, successive multicycle optimization (SCO) is performed for five consecutive cycles of the HPR1000 reactor using deep learning and multi-objective genetic algorithm (MOGA). Ten suitable objective functions were tested. These objective functions were carefully subjected to certain constraints such that the reactor safety criteria are fulfilled in each cycle of MCO. The results of SCO were compared with the reference equilibrium reloadings, and it was concluded that the SCO reloading patterns were safer than the equilibrium reloading patterns by having more margins in the reactor safety criteria at the cost of an average cycle length of 1.6 EFPDs per cycle.

一旦堆芯退出平衡再加载方案，堆芯设计者就需要进行多循环燃料再加载模式优化（MCO）。MCO既可以作为连续多周期优化（也称为逐周期优化）执行，也可以作为同时多周期优化（其中一组周期同时优化）执行。在本研究中，采用深度学习和多目标遗传算法（MOGA）对HPR1000反应器的5个连续循环进行连续多周期优化（SCO）。测试了10个合适的目标函数。这些目标函数仔细地受到某些约束，以便在每个MCO循环中满足反应堆安全标准。将SCO的结果与参考平衡再加载进行了比较，得出的结论是SCO再加载模式比平衡再加载模式更安全，因为它在反应堆安全标准中具有更大的裕度，而代价是每周期平均周期长度为1.6 efpd。

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引用次数: 0

Online fault detection and diagnostics for self powered neutron detector along with its cable using hybrid techniques of noise analysis and clustering algorithm 基于噪声分析和聚类算法的自供电中子探测器及其电缆在线故障检测与诊断

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-06-01 Epub Date: 2026-02-07 DOI: 10.1016/j.anucene.2026.112176

Tahir Kamal Khan , S.R. Shimjith , S. Mukhopadhyay , Ajita Shrivastava

Self-Powered Neutron Detectors (SPNDs) are widely used in large nuclear reactors for in-core flux measurement, supporting monitoring, control, and protection functions. However, SPNDs and their associated cables are prone to aging and degradation, making robust fault detection and diagnosis (FDD) essential for ensuring the safety and reliability of nuclear power plant operations. This work presents a novel hybrid methodology that integrates neutron noise analysis with a K-means clustering algorithm for online, non-intrusive and continuous health monitoring and predictive maintenance of SPNDs and their associated cables. Neutron flux within the reactor core exhibits measurable fluctuations in the 0–20 Hz range due to process-related noise. It is shown that SPNDs’ ability to capture these process related noise characteristics can serve as an effective indicator of their health. A comprehensive SPND model, including its cable and amplifier, is first developed to demonstrate the proposed approach through simulations. A new feature extraction technique is then introduced to characterize the dynamic response obtained from noise analysis, allowing clustering-based classification of SPNDs into healthy, degraded, and severely degraded states. The methodology is validated using plant data from an Indian PHWR employing Inconel SPNDs for safety and control applications. Results show strong agreement with existing offline SPND health assessments, confirming the effectiveness of the proposed approach. Analytical results demonstrate that drift in gain due to insulation resistance reduction of SPNDs is quadratically amplified for power spectral density (PSD) of output signal, leading to enhanced fault sensitivity compared to time-domain representations. This helps to identify faults during clustering. Results have been compared with published literature and are found to be with better accuracy and performance.

自供电中子探测器（SPNDs）广泛应用于大型核反应堆的堆芯通量测量，支持监测、控制和保护功能。然而，spnd及其相关电缆容易老化和退化，因此强大的故障检测和诊断（FDD）对于确保核电站运行的安全性和可靠性至关重要。这项工作提出了一种新的混合方法，将中子噪声分析与k均值聚类算法相结合，用于spnd及其相关电缆的在线、非侵入式和连续健康监测和预测性维护。由于过程相关噪声，反应堆堆芯内的中子通量在0-20 Hz范围内表现出可测量的波动。研究表明，SPNDs捕捉这些过程相关噪声特征的能力可以作为其健康状况的有效指标。首先建立了一个综合的SPND模型，包括其电缆和放大器，通过仿真验证了所提出的方法。然后引入了一种新的特征提取技术来表征噪声分析获得的动态响应，允许基于聚类的spnd分类为健康、退化和严重退化状态。该方法通过使用印度PHWR的工厂数据进行验证，该PHWR采用Inconel spnd用于安全和控制应用。结果显示与现有的离线SPND健康评估非常一致，证实了所提出方法的有效性。分析结果表明，由于spnd的绝缘电阻减小导致的增益漂移在输出信号的功率谱密度（PSD）中被二次放大，与时域表示相比，导致故障灵敏度提高。这有助于在群集过程中识别故障。结果与已发表的文献进行了比较，发现具有更好的准确性和性能。

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引用次数: 0