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Development and verification of the higher-order mode neutron flux calculation code HARMONY2.0

Nuclear science and Techniques 2025年第1期36卷 207-225页

作者： Er-Pin Zhang Zi-Ning Ni Nian-Biao Deng Jin-Sen Xie Yong Liu Tao Yu School of Nuclear Science and Technology University of South ChinaHengyang 421000China Key Laboratory of Advanced Nuclear Energy Design and Safety Ministry of EducationHengyang 421000China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

Higher-order modes of the neutron diffusion/transport equation can be used to study the temporal behavior of nuclear reactors and can be applied in modal analysis, transient analysis, and online monitoring of the reactor core. Both the deterministic method and the Monte Carlo(MC) method can be used to solve the higher-order modes. However, MC method, compared to the deterministic method, faces challenges in terms of computational efficiency and α mode calculation stability, whereas the deterministic method encounters issues arising from homogenization-related geometric and energy spectra *** on the higher-order mode diffusion calculation code HARMONY, we developed a new higher-order mode calculation code, HARMONY2.0, which retains the functionality of computing λ and α higher-order modes from HARMONY1.0, but enhances the ability to treat complex geometries and arbitrary energy spectra using the MC-deterministic hybrid two-step strategy. In HARMONY2.0, the mesh homogenized multigroup constants were obtained using OpenMC in the first step,and higher-order modes were then calculated with the mesh homogenized core diffusion model using the implicitly restarted Arnoldi method(IRAM), which was also adopted in the HARMONY1.0 code. In addition, to improve the calculation efficiency, particularly in large higher-order modes, event-driven parallelization/domain decomposition methods are embedded in the HARMONY2.0 code to accelerate the inner iteration of λ∕α mode using OpenMP. Furthermore, the higher-order modes of complex geometric models, such as Hoogenboom and ATR reactors for λ mode and the MUSE-4 experiment facility for the prompt α mode, were computed using diffusion theory.

关键词： Neutron diffusion equation Higher-order modes Global homogenization Two-step method Domain

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Study on Multi-Motor Synchronization Control for Nuclear Island Main Equipment Transporter Based on Improved Virtual Line-Shafting Structure 11th

Study on Multi-Motor Synchronization Control for Nuclear Isl...

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11th Frontier Academic Forum of Electrical Engineering, FAFEE 2024

作者： Sheng, Beining Song, Beibei An, Yanbo Du, Hua Cui, Shumei School of Electrical Engineering and Automation Harbin Institute of Technology Harbin150001 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789819788231

The existing drive method of the main equipment transporter of the nuclear island makes the transporter have frequent jamming problems when the transporter going straight and turning, which affects the safety during the transporter of the main equipment. Therefore, it is necessary to design an on-board multi-motor synchronous system with differential synchronization function. Although the traditional virtual line-shafting structure has the ability of same-speed synchronization and differential synchronization, there is a large synchronization error. For this reason, this paper proposes a multi-motor synchronous control method based on the improved virtual line-shafting structure, which can effectively solve the inherent synchronous delay problem of the virtual line-shafting. First, analyze and research the combination method of virtual line-shafting structure and deviation coupling structure, and designs the electronic differential to be able to adapt to the requirements of same-speed and differential synchronization. Then the influence of virtual line-shafting parameters on the system is analyzed using the root locus method, and a simplified parameter model of the virtual line-shafting is established, on the basis of which an improved virtual line-shafting control method with low synchronous delay is proposed. The results show that this method can significantly reduce the synchronization error compared with the traditional virtual line-shafting. © Beijing Paike Culture Commu. Co., Ltd. 2025.

关键词： Root loci

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Investigation on influence of gamma irradiation on piezoelectric and resonance characteristics of surface acoustic wave resonators 5

Investigation on influence of gamma irradiation on piezoelec...

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5th International Conference on Mechanical Engineering and Materials, ICMEM 2024

作者： Sun, Lei Peng, Bin Yang, Yuntao Sun, Zhaofeng Zhu, Jialiang Zhang, Wanli State Key Laboratory of Electronic Thin Films and Integrated Devices University of Electronic Science and Technology of China Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (数字)9781510688971

ISBN: (纸本)9781510688964

In this work, an evaluation towards influence of high-dose gamma irradiation on surface acoustic wave (SAW) resonators, is reported. The single-port SAW resonators are fabricated using Lithium niobate (LiNbO3) and Catangasite (CTGS, Ca3TaGa3Si2O14) substrates, along respective cut directions of (0º, 38º, 0º) and (0º, 90º, 0º). Piezoelectric coefficient of substrates, and several main resonance parameters covering resonance frequency, amplitude of resonance peak in reflection coefficient, quality factor together with electromechanical coupling factor of manufactured SAW resonators are investigated, as suitable representatives of piezoelectric and resonance characteristics of SAW resonators. After exposure to gamma ray with a maximum dose of 250 kGy, substrates show insignificant variation not exceeding 6% in their piezoelectric coefficient. Meanwhile, resonance parameters of SAW resonators also alter slightly. Such excellent stability of these characteristics demonstrates credible irradiation hardness owned by both SAW resonators. Results in this study can provide supportive references for usage of LiNbO3 and CTGS-based SAW devices in harsh environments. © 2025 SPIE.

关键词： Gamma rays

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Improving the ductility of laser directed energy deposited borated stainless steel by increasing laser power

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Journal of Manufacturing Processes 2025年 145卷 494-507页

作者： Huang, Sheng Li, Qingyu Zhang, Xiaoyu Cui, Bin Li, Dichen Zhang, Anfeng Miao, Kai State Key Laboratory for Manufacturing Systems Engineering School of Mechanical Engineering Xi'an Jiaotong University Xi'an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Mechanical and Electrical Engineering Yuncheng University Yuncheng044000 China Co. Ltd. Chengdu610091 China

Borated stainless steels (BSSs) are extensively applied in the nuclear energy industry due to boron's excellent thermal neutron absorption capacity, but large and brittle borides formed during casting result in a low ductility. Here, a BSS was produced by laser directed energy deposition, and an investigation was conducted to analyze the impact of laser power on both the microstructure and mechanical properties of the deposited material. Fibrous borides with relatively low volume fraction in the overlapping zone resulted in higher ductility, while lamellar borides with relatively large volume fraction in the non-overlapping zone led to higher strength. As the laser power increased from 180 W to 330 W, the size of fibrous and lamellar eutectic borides and austenite increased significantly, the width of the soft overlapping zone increased by 2.27 times, and the elongation increased by 2.03 times, although yield strength and ultimate tensile strength decreased by 46.3 % and 31.7 %, respectively. As a result, these findings confirmed the feasibility of significantly improving the ductility of the as-deposited BSS by increasing the laser power. The work here provides a way to tailoring the mechanical properties of BSS produced by laser additive manufacturing. © 2025 The Society of Manufacturing Engineers

关键词： Ductility

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Cybersecurity Risk Assessment of Nuclear Svdu Based on Attack Tree

SSRN

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SSRN 2025年

作者： Wu, Yanqun Wang, Junfeng Ma, Quan Liu, Mingxing Chen, Meiyuan College of Computer Science Sichuan University Chengdu610065 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610000 China

The nuclear power SVDU in nuclear power plants is an important component of the nuclear reactor protection system. With the complete digitalization of the reactor protection system, the risks of cybersecurity attacks have significantly increased. This paper proposes a safety risk assessment method based on an attack tree model to analyze the risk status of the nuclear power SVDU and assess its risk level and security level. Firstly, the typical information security threats faced by nuclear power SVDU are analyzed. Subsequently, an attack tree model of the system is constructed based on the STRIDE model, with four security attributes assigned to the leaf nodes of the tree with reference to the CVSS4.0 system and multi-attribute utility theory. These attributes are quantified through level scoring, and the risk probability of the leaf nodes is calculated using entropy weighting. The risk probability of the root node is then obtained based on the dependency relationship between nodes. Finally, the security risk rating of nuclear power SVDU is obtained. Experimental results demonstrate that the method in this paper more accurately identifies high-risk security threats, predicts possible attack paths, and provides a basis for security protection strategy selection. © 2025, The Authors. All rights reserved.

关键词： reactor shielding

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Surface-PMSM Sensorless Control Strategy Based on Reduced-Order Linear Kalman Filter Cooperating with Prediction Error Rolling Compensation

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IEEE Transactions on Power Electronics 2025年

作者： Xu, Sang Shen, Anwen Tang, Qipeng Wang, Miaomiao Luo, Pan Luo, Xin Xu, Jinbang National Key Laboratory of Science and Technology on Multispectral Information Processing Key Laboratory of Image Processing and Intelligent Control School of Artificial Intelligence and Automation Wuhan430074 China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

Kalman filter (KF) is increasingly attracted for sensorless control of surface permanent magnet synchronous motors (SPMSMs) due to its strong robustness against measurement and system noise. However, conventional method suffers from poor position and speed estimation accuracy under dynamic conditions, and high computational cost. In order to solve these problems, an enhanced sensorless control strategy based on reduced-order linear Kalman filter (RLKF) cooperating with prediction error rolling compensation is introduced in this paper. Differing from conventional method, a reduced-order linear state equation encompassing rotor position, speed and torque disturbance is constructed. Then, by obtaining the prediction error of system output using the motor current equation in the predictive reference frame, the optimal estimation of rotor position and speed in KF algorithm is achieved based on the reduced-order model. This not only simplifies the calculation process, but also enhances the position and speed estimation accuracy under dynamic conditions. Meanwhile, a prediction error rolling compensation algorithm is developed to minimize the estimation deviations caused by motor parameters variations. Additionally, the system's dynamic performance is further improved with an adopted speed controller based on torque disturbance feedforward and acceleration feedback. Finally, experimental results verify the effectiveness and feasibility of the proposed strategy.1 © 1986-2012 IEEE.

关键词： Permanent magnets

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Experimental Study on Fretting Wear Characteristic of Zr-4 Alloy

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Yuanzineng Kexue Jishu/Atomic Energy science and technology 2025年第4期59卷 891-899页

作者： Liu, Haidong He, Kai Fu, Jinsheng Li, Zhengyang Pu, Zengping Ren, Quanyao Chen, Deqi Wang, Ningyuan Liangjiang International College Chongqing University of Technology Chongqing401135 China between Chongqing University of Technology Chongqing Research Institute of Harbin Institute of Technology Chongqing401135 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Key Laboratory of Low-grade Energy Utilization Technologies and Systems Ministry of Education Chongqing University Chongqing400044 China

Nuclear energy, as a safe, clean, and efficient low-carbon energy source, has become an important option for achieving sustainable energy and power development. However, during the operation of pressurized water reactors, flow-induced vibrations can trigger fretting wear behavior in Zr-4 alloy cladding, causing damage to the contact surface and leading to the failure of nuclear fuel assemblies, potentially resulting in the leakage of nuclear fission products. To investigate the fretting wear characteristics of Zr-4 alloy cladding, a fretting wear experimental device was independently designed and constructed for studying the wear behavior of Zr-4 alloy under line contact with different displacement amplitudes. The fretting wear of Zr-4 alloy was divided into three zones based on displacement amplitude: low wear zone, accelerated wear zone, and stable wear zone. A white light interferometer was used to obtain the 3D morphology and wear quantities (wear volume and maximum wear depth) of the damaged areas, while scanning electron microscopy (SEM) and energy dispersive spectroscopy (EDS) were used to analyze the microscopic morphology and elemental distribution of the damaged areas. The microstructural characteristics of the fretting wear zones in Zr-4 alloy were studied, focusing on the changes in micro-morphology, elemental composition, and wear mechanisms. The results indicate that an increase in displacement amplitude intensifies the wear phenomena, with maximum wear depth and wear volume increasing. Particularly, in the accelerated wear zone, fretting wear to Zr-4 alloy deteriorates more rapidly. The growth rates of both maximum wear depth and wear volume reach their peak and then decrease. Throughout the fretting wear process, metal oxides such as Zr, Fe, and Cr are generated and removed from the wear zones. The Fe content in the damaged area gradually decreases and stabilizes, while the oxygen content initially increases, reaching a peak in the accelerated wear z

关键词： Cladding (coating)

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Improvement and Validation of system Code for Thermal-hydraulic Analysis of In-pool Passive Residual Heat Removal system

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Yuanzineng Kexue Jishu/Atomic Energy science and technology 2025年第4期59卷 858-866页

作者： Lian, Qiang Zhu, Longxiang Tang, Simiao Huang, Tao Zhang, Yong Pan, Liangming Key Laboratory of Low-grade Energy Utilization Technologies and Systems Ministry of Education Chongqing University Chongqing400044 China Department of Nuclear Engineering and Technology Chongqing University Chongqing400044 China Postdoctoral Station of Power Engineering and Engineering Thermophysics Chongqing University Chongqing400044 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

After Fukushima nuclear accident, the passive concept is widely adopted in the thermal safety design of advanced nuclear reactors. The in-pool passive residual heat removal system (PRHRS) can also provide security guarantee for the domestic reactor HPR1000 without driving of the external power. Although RELAP5 code has been extensively validated for thermal-hydraulic transients in nuclear reactor, it underestimates the heat exchanging power and the system flow rate in the in-pool PRHRS due to the lack of specialized model for in-pool heat exchanger. Therefore, the model development for the in-pool heat exchanger is necessary for accurate simulation of PRHRS and safety assessment of the reactor system. In this study, the in-pool bundle boiling model and large-diameter tube condensation model were selected and implemented in RELAP5 code as the in-pool heat exchanger model. Firstly, the relevant heat transfer models in original RELAP5 were evaluated. The results show that Chen correlation developed initially for in-tube boiling is not suitable for bundle boiling heat transfer. Thus Cooper correlation developed initially for in-pool boiling considering the surface roughness is used to replace Chen correlation for the bundle geometry. On the other hand, the calculation in original RELAP5 for in-tube condensation encounters some faults under the condition with low gas speed in the natural circulation of PRHRS. The Shah method modified through fluid viscosity and pressure is chosen for the calculation of condensation heat transfer coefficient in the large-diameter tube. Secondly, the separate effect validation was carried out for the two heat transfer models. For the validation of in-pool bundle boiling model, the root-mean-square error of the heat transfer coefficient predicted by the improved RELAP5 is reduced to 16.2%, compared to the value of 53.8% obtained by the original code. For the validation of in-tube condensation model, the root-mean-square error of the heat fl

关键词： Nuclear reactor accidents

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Deep learning-based dual monitoring system for power forecasting and fault detection in nuclear power applications

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Energy and AI 2025年 20卷

作者： Lyu, Mingzhe Gong, Helin Chen, Zhang Wang, Jiangyu Zhong, Mingxiao Wang, Zhiyong Li, Qing Pan, Zefei School of Mathematical Sciences University of Electronic Science and Technology of China Chengdu611731 China Shanghai Zhangjiang Institute of Mathematics Shanghai201203 China Paris Elite Institute of Technology Shanghai Jiao Tong University Shanghai200240 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China CNNP Operation Maintenance Technology Co. Ltd Hangzhou311215 China

Monitoring key parameters in nuclear power plant control rooms is critical, as human errors can result in severe safety and operational consequences. This study proposes a hybrid framework for power prediction and fault detection that integrates multi-head self-attention mechanisms with long short-term memory networks, combined with a dual-monitoring system. The framework is evaluated using real-time data from two pressurized water reactor units (Units 5 and 6) under four realistic operational scenarios. In the most informative case, the model achieves a 56.6% reduction in root mean square error and a 36.8% reduction in mean absolute error, with a coefficient of determination (R2) of 0.9924—significantly outperforming the next-best benchmark. For fault diagnosis, the dual-monitoring system reduces the false negative rate to 18.73% and improves recall to 81.27%, demonstrating strong anomaly detection under complex conditions. By combining short-term fluctuation sensitivity with long-term trend stability, the proposed approach offers a robust and generalizable solution for intelligent monitoring. These findings advance the development of artificial intelligence–enhanced systems for secure and efficient operation of critical energy infrastructure. © 2025 The Authors

关键词： Deep learning

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The role of secondary phases on SCC initiation of Alloy 718 in simulated PWR primary water

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Corrosion science 2025年 252卷

作者： Zhu, Tianyu Wang, Jiamei Song, Miao Ren, Quanyao Qiu, Xi Li, Yuanming Tang, Chuanbao Yi, Hongpu Zhang, Jing Tian, Wenxi Ang, Y.U. Guo, Xianglong School of Nuclear Science and Engineering Shanghai Jiao Tong University No. 800 Dongchuan Road Shanghai200240 China Ministry of Education China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China School of Energy and Power Engineering Xi'an Jiao Tong University Xi'an710049 China Baimtec Material Co. Ltd Beijing100095 China

Stress corrosion cracking (SCC) initiation behavior of Alloy 718 with different precipitates was studied by slow strain rate tensile testing (SSRT) in a simulated pressurized water reactor (PWR) primary water environment. It was found that both nano-precipitates (γ', γ'' phases) and δ phases enhanced the SCC susceptibility. Nano-precipitates significantly suppressed the interior slip and increased the local stress concentration at grain boundaries (GBs), thus promoting the initiation of intergranular (IG) cracks. GBs oriented perpendicular to the loading direction favored IG crack propagation. Preferential oxidation of the δ phases and the δ/γ interface were precursors to crack initiation, thereby increasing the SCC susceptibility. The shape of δ phases affected the oxidation degree, and more severe oxidation was observed on needle-like δ phases. © 2025 Elsevier Ltd

关键词： Stress corrosion cracking

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