百晓学者学者目录

彭敏俊

哈尔滨工程大学核安全与仿真技术国防重点学科实验室

个人简介

彭敏俊，男，汉族，1968年4月生，籍贯云南省曲靖市，中共党员，工学博士，哈尔滨工程大学核科学与技术学院教授、博士生导师，核安全与仿真技术国防重点学科实验室成员，研究方向为核科学技术、计算机软件及计算机应用、自动化技术。

精选作品

期刊论文

  1. 张彪，蔡幸福，李国强，李晓梦，彭敏俊（2026）. 核设施放射性环境中A*算法改进及其路径平滑优化研究. 《原子能科学技术》.
  2. 刘亦然，周建平，彭敏俊，张薇，商超皓（2026）. 压水堆抽汽供热智能控制方法研究. 《核科学与工程》.
  3. 李子康，王航，彭敏俊，虞越（2026）. 联合PCA和因果网络的核电厂异常监测与溯源分析方法研究. 《核动力工程》.DOI
  4. Xinheng Zhao, Minjun Peng, Guangliang Chen (2026). A real-time digital twin framework for rod-bundle hydraulics using POD-based surrogates and FMI-compliant system coupling. Annals of Nuclear Energy.DOI
  5. He Shang, Min-Jun Peng, Yi-Fan Xu, G. Xia (2026). A parametric nonlinear model reduction method for the flow field in the RPV lower plenum using KPCA and sparse grids. Nuclear Engineering and Design.DOI
  6. Yi-Fan Xu, Xiao-Bo Zeng, Chen-Yang Wang, G. Xia, Min-Jun Peng (2026). A data-driven reduced-order modeling approach for state estimation in IPWR forced-to-natural circulation transitions. Nuclear Engineering and Design.DOI
  7. Yi-Ming Xiong, Ren Li, Ji-Lin Sun, Yuan-Dong Zhang, G. Xia, Min-Jun Peng (2026). Design and performance analysis of high-power lead-bismuth cooled micro reactor. Annals of Nuclear Energy.DOI
  8. F. Haseeb, Minjun Peng, Furqan Arshad, Khan Awais, Wasiq Ali (2026). Hybrid data augmentation for uncertainty mitigation in machine learning based fault diagnosis of pressurized water reactor nuclear power plants. Nuclear Engineering and Technology.DOI
  9. F. Haseeb, Minjun Peng, Furqan Arshad, Wasiq Ali (2026). Uncertainty aware unsupervised fault diagnosis of PWR nuclear power plant using KNN and SHAP method. Progress in nuclear energy (New series).DOI
  10. Festus Ojonugwa Ocheme, Yu Lei, Minjun Peng (2026). Fluka-informed surrogate modelling: A physics-aligned approach to anticipate cooling faults in spent nuclear fuel pools. Annals of Nuclear Energy.DOI
  11. S. Lawal, Chen-Yang Wang, Minjun Peng (2026). Reliability of passive safety system in nuclear power plants: advances, emerging technologies, and persistent challenges. Annals of Nuclear Energy.DOI
  12. Furqan Arshad, Minjun Peng, Wasiq Ali, Zikang Li, F. Haseeb, Awais Khan (2026). Physics-informed fault diagnosis through online efficiency monitoring of PWR type nuclear power plants. Annals of Nuclear Energy.DOI
  13. Xin Wang, Hang Wang, Minjun Peng, Yuanli Sun, Chengming Hao (2026). Robust and interpretable fault diagnosis for nuclear power plants using fault causal graph neural networks. Engineering Applications of Artificial Intelligence.DOI
  14. Yan Cui, Yu Sun, Hang Wang, Shijun Chen, Hebin Ren, Minjun Peng, Ruixin Lu (2026). Fault Diagnosis for Key Nuclear Power Plant Systems and Equipment Based on Knowledge Graphs and Bayesian Networks. Processes.DOI
  15. Ziqiang Zhou, Pengfei Zhang, Minjun Peng, Xi Zhang (2026). Numerical study on vibration characteristics of U-tube bundles in nuclear power plant steam generators. Journal of Physics Conference Series.DOI
  16. Ruo-Jun Xue, Han-Wen Liang, Hao-Fang Chong, Minjun Peng (2026). Operational strategies for nuclear district heating systems in extremely cold climates. Annals of Nuclear Energy.DOI
  17. Yiming Xiong, Minjun Peng, Genglei Xia, J.G. Sun (2026). Simulation Method of Supercritical Carbon Dioxide (sCO2) Cycle System Based Fluid Networks. Springer proceedings in physics.DOI
  18. Hongyuan Chen, Hang Wang, Minjun Peng (2026). Distinction Between Single and Multiple Sensor Failures Under Variable Working Conditions in Nuclear Power Plants. Lecture notes in mechanical engineering.DOI
  19. Hang Wang, Yu Sun, Fangxiaozhi Yu, Minjun Peng (2026). Research on Intelligent Diagnosis Methods for Nuclear Reactor Primary Loop System Faults Driven by Expert Knowledge and Data Integration. Lecture notes in mechanical engineering.DOI
  20. Xin Wang, Hang Wang, MinJun Peng (2025). Interpretability study of a typical fault diagnosis model for nuclear power plant primary circuit based on a graph neural network. Reliability Engineering & System Safety, Vol. 261.DOI
  21. 汪鑫，王航，彭敏俊（2025）. 知识-数据融合的核电厂异常诊断模型研究. 《哈尔滨工程大学学报》.
  22. 商贺，彭敏俊，夏庚磊，张世琦，朱世杰（2025）. 二维下腔室稳态流场降阶模型开发. 《原子能科学技术》.
  23. 王晓昆，王航，邓强，刘诗文，彭敏俊，徐仁义（2025）. 基于1.5维谱WHNR优化CVMD的滚动轴承特征增强方法. 《振动、测试与诊断》.DOI
  24. Miao Yang, Xingfu Cai, Minjun Peng, Ya-Pei Zhang, Hao-Li Wang, Hao-Wei Wang, Biao Zhang (2025). Study on the release and migration of radioactive materials under LBLOCA in small pressurized water reactor. AIP Advances.DOI
  25. Biao Zhang, Xingfu Cai, Guoqiang Li, Xiaomeng Li, Minjun Peng, Miao Yang (2025). A modified A* algorithm for path planning in the radioactive environment of nuclear facilities. Annals of Nuclear Energy.DOI
  26. Biao Zhang, Xingfu Cai, Guoqiang Li, Xiaomeng Li, Minjun Peng, Hao-Wei Wang (2025). Path planning in radioactive environment of nuclear facilities based on modified A-star algorithm and search neighborhood optimization. Nuclear Engineering and Technology.DOI
  27. Yu-Chen Niu, Dabin Sun, Yuan-Dong Zhang, Lei Chen, Min-Jun Peng, G. Xia (2025). Operation characteristics analysis of supercritical CO2 reactor based on neutronics and thermal-hydraulics coupling. Nuclear Engineering and Design.DOI
  28. Min-Jun Peng, Zhaofei Tian, G. Xia, Hang Wang (2025). Thermal Analysis of Nuclear Power Plants. Nuclear Science and Technology.DOI
  29. Ren Li, Xu Yang, Haoxiang Xu, Yuan-Dong Zhang, G. Xia, Min-Jun Peng (2025). Analysis and optimization of operating characteristics for integrated pressurized water reactor IP200. Annals of Nuclear Energy.DOI
  30. Hao-Fang Chong, Ruo-Jun Xue, C. Gao, Guang-Liang Chen, Min-Jun Peng (2025). Design and analysis of a nuclear heating system integrated with molten salt energy storage. Annals of Nuclear Energy.DOI
  31. Chen-Yang Wang, Jia-Wei Zhou, Yi-Fan Xu, G. Xia, Min-Jun Peng (2025). Machine learning-based water-level forecasting for marine steam generators under rolling conditions. Nuclear Engineering and Design.DOI
  32. Guang-Hui Jiao, G. Xia, Tao Zhou, Min-Jun Peng, Jianjun Wang (2025). Transient local effects analysis during typical accidents of a heat pipe cooled reactor. Nuclear Engineering and Design.DOI
  33. Yuan-Dong Zhang, Ren Li, Bowen Zhang, Y. Miao, Chao Guo, G. Xia, Min-Jun Peng (2025). Design and performance analysis of 15MWth SCO2-cooled micro reactor. Nuclear Engineering and Technology.DOI
  34. Yuepeng Bi, G. Xia, Chen-Yang Wang, Min-Jun Peng, Yi-Fan Xu, Jiebo Wu (2025). Design and transient analysis of a novel type passive residual heat removal system. Nuclear Engineering and Design.DOI
  35. Furqan Arshad, Minjun Peng, F. Haseeb, Wasiq Ali (2025). An intelligent fault detection method for PWR-type nuclear power plants using neuro-encoder binary cells. Nuclear Engineering and Technology.DOI
  36. J. Shui, Chunhui Dong, Fuqiu Ma, Minjun Peng, Wenxiu Yang (2025). Effects of Feedback Color and Icon Shape on Touch Interaction Performance Under Unstable Conditions of Floating Nuclear Power Platforms. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
  37. Hang Wang, Hongyuan Chen, Fangxiaozhi Yu, Zhao Xu, Minjun Peng (2025). Anomaly detection and reconstruction of sensors in nuclear power plants based on principal component analysis and improved deep neural networks. Progress in Nuclear Energy.DOI
  38. Yuchen Niu, Yuandong Zhang, Minjun Peng, Genglei Xia (2025). Analysis of Control Principles for SCO2 Reactor System Based on Modelica. International Conference on Power and Renewable Energy (ICPRE).DOI
  39. Mengyao Ma, Hang Wang, Minjun Peng, Hongyuan Chen (2025). Cointegration analysis-based fault diagnosis and reconstruction model for non-stationary sensor signals in nuclear power plants under variable operating conditions. Nuclear Engineering and Design.DOI
  40. Zikang Li, Hang Wang, Li Fei, Minjun Peng, Zhang Xian, Gui Feng Zhou (2025). Multi-parameter optimization of NPP simulation models using enhanced particle swarm method. Progress in Nuclear Energy.DOI
  41. Chen Li, Xinkai Liu, Hang Wang, Minjun Peng (2025). Fault Diagnosis Method for Centrifugal Pumps in Nuclear Power Plants Based on a Multi-Scale Convolutional Self-Attention Network. Sensors.DOI
  42. 许依凡，彭敏俊，夏庚磊（2024）. 直流蒸汽发生器参数化降阶建模. 《哈尔滨工程大学学报》.
  43. 王晨阳，夏庚磊，彭敏俊，徐青蓝，陈果（2024）. 基于自适应代理模型的非能动系统可靠性分析. 《哈尔滨工程大学学报》.
  44. 许依凡，彭敏俊，夏庚磊（2024）. 基于动态模式分解的直流蒸汽发生器降阶建模. 《核动力工程》.
  45. 张世琦，彭敏俊，夏庚磊，王晨阳，商贺（2024）. 海洋条件下非能动系统高效全局敏感性分析方法研究. 《核技术》.
  46. 焦广慧，代丽红，夏庚磊，王建军，彭敏俊（2024）. 基于多物理耦合的高温热管流动传热和力学特性研究. 《原子能科学技术》.
  47. Wei Guo, Bo Shi, Tao Zhang, Zhijiang Wu, Guohua Xiong, Minjun Peng (2024). Research on Active Disturbance Rejection Control of Small Modular Reactor Once-Through Steam Generator Based on Differential Evolution Optimization Algorithm. Nuclear Technology.DOI
  48. Xiang Zhang, G. Xia, Tenglong Cong, Min-Jun Peng (2024). Numerical investigation on boiling crisis in a full-length 5 × 5 fuel assembly under typical pressurized water reactor conditions. International Journal of Heat and Mass Transfer.DOI
  49. He Shang, Min-Jun Peng, G. Xia, Shiqi Zhang, Shijie Zhu (2024). Development of a Nonintrusive ROM for Parametric Study in the RPV Lower Plenum. Volume 11: Student Paper Competition.DOI
  50. Yuepeng Bi, G. Xia, Chen-Yang Wang, Min-Jun Peng, Chang Wang, Chengyan Gu (2024). Research on reliability assessment approach of marine passive safety system based on improved Kriging model and SORM. Annals of Nuclear Energy.DOI
  51. Shiqi Zhang, Min-Jun Peng, G. Xia, Chen-Yang Wang, He Shang (2024). An active learning approach for reliability assessment of passive systems combining polynomial chaos expansion and adaptive sampling. Nuclear Engineering and Design.DOI
  52. Shuaijie Lu, G. Xia, Min-Jun Peng, Bowen Zhang (2024). A thermal-hydraulic and control model for a Pb-Bi micro reactor. Annals of Nuclear Energy.DOI
  53. Yi-Fan Xu, Min-Jun Peng, G. Xia (2024). Application of Modal Decomposition Techniques for Reduced-Order Modelling of Once-Through Steam Generator. Volume 6: Thermal-Hydraulics and Safety Analysis.DOI
  54. Yi-Fan Xu, Min-Jun Peng, G. Xia, Xiao-Bo Zeng (2024). Parametric reduced-order modeling of once-through steam generator via double proper orthogonal decomposition. Nuclear Engineering and Design.DOI
  55. Yi-Fan Xu, Min-Jun Peng, A. Cammi, C. Introini, G. Xia (2024). Model order reduction of a once-through steam generator via dynamic mode decomposition. Annals of Nuclear Energy.DOI
  56. Gui Feng Zhou, Minjun Peng, Hang Wang, Dabin Sun, Zi-kang Li (2024). Research on fault diagnosis method and interpretability of nuclear power plant based on hybrid transformer model. Annals of Nuclear Energy.DOI
  57. Zhe Yuan, Bowen Zhang, Minjun Peng, Chengyan Gu, Ke Su, Chenxing Yan (2024). Intelligent Control Method for SCO2 Brayton Cycle Reactors. International Conference on Intelligent Control, Measurement and Signal Processing (ICMSP).DOI
  58. Furqan Arshad, Minjun Peng, Wasiq Ali, Zikang Li, Hang Wang (2024). Optimized utilization of neural networks for online efficiency monitoring and fault detection in PWR nuclear power plant. Annals of Nuclear Energy.DOI
  59. Renyi Xu, Yan Wang, Minjun Peng, Huaiming Cui, Hang Wang, Chengxiao Kuang (2024). Predictions of Component Remaining Useful Life Using Bayesian LSTM for Reactor Coolant Pump.DOI
  60. Xin Wang, Minjun Peng, Hang Wang, Zikang Li (2024). Typical Fault Diagnosis Model of Nuclear Power Plant Combined With Knowledge Driven and Data Driven.DOI
  61. Niu Yuchen, Minjun Peng, Bowen Zhang, Zhe Yuan (2024). Research on Operation and Control Characteristics of Large Parallel Pipeline Fluid System.DOI
  62. 周桂，王航，彭敏俊（2023）. 混合神经网络的核电站故障程度评估方法. 《哈尔滨工程大学学报》.
  63. 徐仁义，王航，彭敏俊，刘永阔，虞越，艾鑫（2023）. 核电厂智能操纵员支持系统的设计与开发. 《核动力工程》.
  64. 邓强，王航，彭敏俊，王晓昆，徐仁义（2023）. 基于时间卷积胶囊网络的核动力装置事故诊断技术研究. 《原子能科学技术》.
  65. 夏庚磊，孙觊琳，彭敏俊（2023）. 线上线下混合的虚拟仿真实验教学模式探究与实践. 《大学》.
  66. 彭敏俊（2023）. 核动力装置热力分析. 《哈尔滨工程大学出版社》.
  67. 夏庚磊，张博文，彭敏俊（2023）. 基于虚拟仿真技术的多元混合线上教学模式探讨. 《信息系统工程》.
  68. Guang-Hui Jiao, G. Xia, Min-Jun Peng, Yuangdong Zhang, Jian-Jun Wang (2023). TRANSIENT NUCLEAR THERMAL COUPLING CHARACTERISTICS OF A MEGAWATT HEAT PIPE COOLED REACTOR. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  69. Guang-Hui Jiao, G. Xia, Jian-Jun Wang, Min-Jun Peng (2023). Thermal-hydraulic and load following performance analysis of a heat pipe cooled reactor. Nuclear Engineering and Technology.DOI
  70. Shiqi Zhang, Min-Jun Peng, G. Xia, Chen-Yang Wang (2023). SENSITIVITY ANALYSIS BASED ON ELEMENTARY EFFECTS AND VARIANCE METHOD OF PASSIVE SYSTEM PERFORMANCE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  71. Xiang Zhang, G. Xia, Min-Jun Peng, Chunyan He, Tenglong Cong, Haoqi Yu (2023). Numerical study on a semi-mechanistic wall boiling model based on dry-patch mechanism for CHF prediction in vertical tube and fuel assembly. Annals of Nuclear Energy.DOI
  72. Zhanguo Ma, Shiguang Deng, Zhuoran Zhou, Xin Ai, Jing Zhang, Yong-kuo Liu, Minjun Peng, Jing Cui (2023). Expert knowledge modelling software design based on Signed Directed Graph with the application for PWR fault diagnosis. Annals of Nuclear Energy.DOI
  73. Guanghui Jiao, Genglei Xia, Haishan Zhu, Tao Zhou, Minjun Peng (2023). Thermal-mechanical coupling characteristics and heat pipe failure analysis of heat pipe cooled space reactor. Annals of Nuclear Energy.DOI
  74. Hanan A. Saeed, Minjun Peng, Hang Wang, Athar Rasool (2023). Autonomous control model for emergency operation of small modular reactor. Annals of Nuclear Energy.DOI
  75. Xiang Zhang, Ren Li, Minjun Peng, Tenglong Cong, Chunyan He, Genglei Xia, Xiaojing Wei (2023). Numerical analysis on subcooled boiling in PWR coolant channel based on a modified multi-scale interface model. Applied Thermal Engineering.DOI
  76. Shiqi Zhang, Genglei Xia, Minjun Peng, Chenyang Wang (2023). Reliability assessment of passive residual heat removal system using FORM methodology with chaos control. Annals of Nuclear Energy.DOI
  77. 孙觊琳，成守宇，薛若军，张博文，彭敏俊（2022）. 开放式实验在“核工程虚拟仿真实验”课程教学中的应用初探. 《现代信息科技》.
  78. 徐仁义，王航，彭敏俊，刘永阔，邓强（2022）. 核电厂电动闸阀外漏故障预测方法研究. 《哈尔滨工程大学学报》.
  79. 徐仁义，王航，彭敏俊，邓强，王晓昆（2022）. 剩余寿命预测新方法及其在滚动轴承中的应用. 《振动、测试与诊断》.
  80. Bello Mary Olubunmi, Min-Jun Peng, G. Xia (2022). THE EFFECTS OF SYSTEM PARAMETERS ON THE INCEPTION OF FLASHING USING RELAP5. MATTER: International Journal of Science and Technology.DOI
  81. Bello Mary Olubunmi, Min-Jun Peng, G. Xia (2022). The Effects of System Parameters on Inception of Flashing using Relap5. MATTER International Journal of Science and Technology.DOI
  82. Ziakng Li, Hang Wang, Minjun Peng, Renyi Xu, Yue Yu, Gui Feng Zhou (2022). Digital Twin Based Operation Support System of Nuclear Power Plant. IEEE International Conference on Digital Twins and Parallel Intelligence (DTPI).DOI
  83. Bowen Zhang, Shibo Wang, Shouyu Cheng, J.G. Sun, Minjun Peng, Chenyang Wang (2022). Transient trend prediction of safety parameters for small modular reactor considering equipment degradation. Annals of Nuclear Energy.DOI
  84. Yifan Xu, Minjun Peng, Genglei Xia (2022). An improved-MPGA and its application in OTSG load reduction characteristics optimization. Annals of Nuclear Energy.DOI
  85. Ji-lin Sun, Bowen Zhang, Shouyu Cheng, Minjun Peng (2022). Investigation of single pressure point off-line correction in matrix-solved steam pipe network model for digital twins application. Annals of Nuclear Energy.DOI
  86. Shuaijie Lu, Minjun Peng, Genglei Xia, Qianping Zhang (2022). Simulation study on thermal characteristics of primary coolant system of lead-bismuth cooled reactor. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
  87. Zhuoran Zhou, Minjun Peng, Hang Wang, Yingying Jiang (2022). Modeling and Fault Diagnosis of Pressurizer Based on Bond Graph. Volume 15: Student Paper Competition.DOI
  88. Zhuoran Zhou, Zhanguo Ma, Yingying Jiang, Minjun Peng (2022). Fault Diagnosis Using Bond Graphs in an Expert System. Energies.DOI
  89. Hao Yu, Naiyan Shao, Genglei Xia, Minjun Peng (2022). Development of two-dimensional hydrogen distribution model in small-scale spaces under severe accidents. Nuclear Engineering and Design.DOI
  90. Yue Yu, Minjun Peng, Hang Wang, Zhanguo Ma (2022). Multivariate Alarm Threshold Design Based on PCA. Lecture notes in mechanical engineering.DOI
  91. Renyi Xu, Minjun Peng, Hang Wang (2022). Study on the Condition Monitoring Technology of Electric Valve Based on Principal Component Analysis. Lecture notes in mechanical engineering.DOI
  92. Hanan A. Saeed, Peng Minjun, Hang Wang (2022). Fault Diagnosis Capability of Shallow vs Deep Neural Networks for Small Modular Reactor. Lecture notes in mechanical engineering.DOI
  93. 许依凡，彭敏俊，夏庚磊（2021）. 基于Sobol方法的OTSG运行参数敏感性分析. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第2册（核能动力分卷）》.DOI
  94. 郑勇，彭敏俊，安萍，强胜龙，芦韡（2021）. 基于CUDA并行技术加速2维矩阵MOC方法的研究. 《科技视界》.DOI
  95. 王航，彭敏俊，薛若军，王贺，夏庚磊（2021）. 高校线上教学模式思考与创新——以“核动力装置与设备”为例. 《科教文汇》.
  96. Xiang Zhang, Minjun Peng, Tenglong Cong, Chuan Jing Lu, Chenyang Wang (2021). Implementation and Validation of an Improved Interfacial Area Concentration Model for Two-Phase Flow CFD Simulations.DOI
  97. Zhenhang Zheng, Minjun Peng, Hao Yu, Yang Yang (2021). Analysis of IP200 Severe Accident Process Response to SBO and Emergency Power Failure.DOI
  98. Zikang Li, Minjun Peng (2021). Research on Remaining Useful Lifetime Prediction Methods of Main Transformer in Nuclear Power Station.DOI
  99. Jing Luo, Hang Wang, Minjun Peng (2021). Anomaly Detection of Electric Gate Valve Based on Multi-Kernel Support Vector Machine.DOI
  100. Gui Feng Zhou, Hang Wang, Minjun Peng (2021). Research on Optimization and Verification Method of Sensor Arrangement in the Chemical and Volume Control System.DOI
  101. Hao Yu, Minjun Peng (2021). Analysis of IPWR Severe Accident Process Response to SBLOCA.DOI
  102. Xiang Zhang, Minjun Peng, Tenglong Cong, Genglei Xia, Abdullah A.M. Rawashdeh (2021). Studies on the critical heat flux in fuel assembly using a modified two-phase multi-scale interface model—validation and sensitivity analysis. International Journal of Heat and Mass Transfer.DOI
  103. Yifan Xu, Minjun Peng, Genglei Xia, Shang He (2021). Optimization of forced circulation to natural circulation transition characteristics of IPWR. Annals of Nuclear Energy.DOI
  104. Ruiqi Li, Minjun Peng, Genglei Xia, H. Li (2021). The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition. Kerntechnik.DOI
  105. Lin Fu Sun, Minjun Peng, Genglei Xia, Xuesong Wang, Mingyu Wu (2021). Development and Validation of Multiscale Coupled Thermal-Hydraulic Code Combining RELAP5 and Fluent Code. Frontiers in Energy Research.DOI
  106. 彭彬森，夏虹，朱少民，彭敏俊，刘永阔，马心童（2020）. 核动力装置运行数据的特征提取方法研究. 《原子能科学技术》.
  107. 张翔，彭敏俊，丛腾龙，李孝佳，陈衣然（2020）. 基于确定性抽样的过冷沸腾边界条件不确定性分析. 《原子能科学技术》.
  108. Hao Yu, Minjun Peng, Nan Jiang, Hang Wang (2020). Model development for the transient heat transfer in a corium pool. Nuclear Engineering and Design.DOI
  109. Xiang Zhang, Genglei Xia, Tenglong Cong, Minjun Peng, Zhenhong Wang (2020). Uncertainty Analysis on k-ε Turbulence Model in the Prediction of Subcooled Boiling in Vertical Pipes. Frontiers in Energy Research.DOI
  110. Hang Wang, Minjun Peng, Renyi Xu, Abiodun Ayodeji, Hong Xia (2020). Remaining Useful Life Prediction Based on Improved Temporal Convolutional Network for Nuclear Power Plant Valves. Frontiers in Energy Research.DOI
  111. Yifan Xu, Minjun Peng, Genglei Xia, Yanan Zhao (2020). Validation of RELAP5/MOD3.4 for Flashing-Induced Instabilities in a Natural Circulation Loop.DOI
  112. Yuandong Zhang, Minjun Peng, Genglei Xia, Lianxin Lv (2020). Transient thermal–hydraulic analysis of SCO2-cooled reactor system with modified RELAP5. Annals of Nuclear Energy.DOI
  113. Yanan Zhao, Minjun Peng, Yifan Xu, Genglei Xia (2020). Simulation investigation on flashing-induced instabilities in a natural circulation system. Annals of Nuclear Energy.DOI
  114. Yuandong Zhang, Minjun Peng, Genglei Xia, Ge Wang, Cheng Zhou (2020). Performance analysis of S-CO2 recompression Brayton cycle based on turbomachinery detailed design. Nuclear Engineering and Technology.DOI
  115. Yanan Zhao, Minjun Peng, Genglei Xia (2020). Safety evaluation of the flashing-driven natural circulation IPWR against Loss-of-Feedwater accident. Annals of Nuclear Energy.DOI
  116. Li Ren, Minjun Peng, Genglei Xia, Lin Sun (2020). The natural circulation flow characteristic of the core in floating nuclear power plant in rolling motion. Annals of Nuclear Energy.DOI
  117. Hanan A. Saeed, Hang Wang, Minjun Peng, Anwar Hussain, Amjad Nawaz (2020). Online fault monitoring based on deep neural network & sliding window technique. Progress in Nuclear Energy.DOI
  118. 杨旭，邱金荣，杨永强，彭敏俊，侯晓凡，王世明（2019）. 反应堆准确实时仿真程序的开发. 《核安全》.DOI
  119. 张博文，彭敏俊，成守宇（2019）. 强迫转自然循环一体化压水堆协调控制策略. 《哈尔滨工程大学学报》.
  120. 夏虹，刘正，彭敏俊，田凯，马福秋，李体强，曹婉璐（2019）. “订单+联合”大核电人才培养模式在校企合力作用下对学生实践能力的影响. 《教育现代化》.
  121. Lin Fu Sun, Minjun Peng, Genglei Xia, Jun Wang, Ruiqi Li (2019). Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident. Kerntechnik.DOI
  122. Meijie Gong, Minjun Peng, Haishan Zhu (2019). Research of quasi 2-D refined simulation and modeling for deaerator in nuclear power plant. Annals of Nuclear Energy.DOI
  123. Songsheng Tang, Minjun Peng, Genglei Xia, Ge Wang, Cheng Zhou (2019). Optimization design for supercritical carbon dioxide compressor based on simulated annealing algorithm. Annals of Nuclear Energy.DOI
  124. Chenyang Wang, Minjun Peng, Genglei Xia (2019). Sensitivity analysis based on Morris method of passive system performance under ocean conditions. Annals of Nuclear Energy.DOI
  125. Nan Jiang, Minjun Peng, Tenglong Cong (2019). Thermal margin evaluation for the stratified molten pool in SMR-IP200. Nuclear Engineering and Design.DOI
  126. Hao Yu, Minjun Peng (2019). Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario. Science and Technology of Nuclear Installations.DOI
  127. Meijie Gong, Minjun Peng, Haishan Zhu (2019). Research of parameter distributing simulation and modeling for the condenser in nuclear power plant. Annals of Nuclear Energy.DOI
  128. Li Ren, Genglei Xia, Minjun Peng, Lin Fu Sun (2019). The simulation study on natural circulation operating characteristics of FNPP in inclined condition. Nuclear Engineering and Technology.DOI
  129. Nan Jiang, Minjun Peng, Tenglong Cong (2019). Flow instability analysis of natural circulation under ERVC condition for SMR. Progress in Nuclear Energy.DOI
  130. Yanan Zhao, Minjun Peng, Yifan Xu, Genglei Xia, Chang Wang (2019). Analysis of the transient performance of the flashing-driven natural circulation IPWR. Annals of Nuclear Energy.DOI
  131. Jianchuang Sun, Ruibin Xue, Minjun Peng (2019). Research on multi-scale simulation model for single-phase water pipe networks. Kerntechnik.DOI
  132. Yuandong Zhang, Minjun Peng, Genglei Xia, Tenglong Cong (2019). Numerical investigation on local heat transfer characteristics of S-CO2 in horizontal semicircular microtube. Applied Thermal Engineering.DOI
  133. Xing Lyu, Minjun Peng, Genglei Xia (2019). Analysis of start-up and long-term operation characteristics of passive residual heat removal system. Annals of Nuclear Energy.DOI
  134. Lin Fu Sun, Minjun Peng, Genglei Xia, Bowen Zhang, Ren Li (2019). Analysis of IPWR neutronic-thermohydraulic operation characteristics under low power condition. Annals of Nuclear Energy.DOI
  135. Chenyang Wang, Minjun Peng, Tenglong Cong, Genglei Xia (2019). Uncertainty analysis on natural circulation characteristics under ocean conditions. Annals of Nuclear Energy.DOI
  136. Miaomiao Han, Zhirong Guo, Haifeng Liu, Minjun Peng, Qinghua Li, Xianglei Chen (2019). Evaluation of an emission path length computation model applied at different resolutions in Tomographic Gamma Scanning. Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment.DOI
  137. Chenyang Wang, Minjun Peng, Genglei Xia, Tenglong Cong (2019). Reliability assessment of passive residual heat removal system of IPWR using Kriging regression model. Annals of Nuclear Energy.DOI
  138. Bowen Zhang, Minjun Peng, Shouyu Cheng, Lin Fu Sun (2019). SELECTING FEATURES FOR INTEGRATED PRESSURIZED WATER REACTOR’S BEHAVIOR PREDICTION USING MACHINE LEARNING. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  139. Zhanguo Ma, Minjun Peng, Hidekazu Yoshikawa, Huayu Yuan, Bo YANG (2019). A SAFETY-CRITICAL SOFTWARE RELIABILITY ANALYSIS METHOD BASED ON STATISTICAL MODEL CHECKING AND BAYESIAN THEORY. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  140. Yuandong Zhang, Minjun Peng, Genglei Xia, Songsheng Tang, Ge Wang, Cheng Zhou (2019). INVESTIGATION ON DESIGN AND ANALYSIS OF S-CO2 TURBOMACHINERY. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  141. Chenyang Wang, Minjun Peng, Genglei Xia (2019). RELIABILITY ASSESSMENT OF A PASSIVE RESIDUAL HEAT REMOVAL SYSTEM WITH AN ADAPTVIE SAMPLING METHOD. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  142. Jie Liu, Minjun Peng, Hang Wang, Meijie Gong (2019). DEVELOPMENT OF DISTRIBUTED PERFORMANCE MONITORING AND ANALYSIS SYSTEM FOR NUCLEAR POWER PLANT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  143. Zheng Yong, Peng Minjun, Ping An, Wei Lu (2019). AN ACCELERATION TECHNIQUE FOR METHOD OF CHARACTERISTICS BASED ON PRECONDITIONING METHOD AND CUDA TECHNIQUE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  144. Zhang Pengfei, Peng Minjun, ZHANG Yi, Yan Chao-xing (2019). MULTIPLE TARGETS OPTIMIZATION DESIGN OF NUCLEAR POWER PLANT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  145. Xu Yang, Qiu Jin-rong, Yongqiang Yang, Hou Xiaofan, Peng Minjun, Jie Liu, Longze Li (2019). THE RESEARCH OF CORE ON-LINE MONITORING TECHNOLOGY BASED ON SIMULATION MODEL. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  146. 李伟，彭敏俊，刘永阔（2018）. 基于PCA的核电站传感器状态监测方法研究. 《核动力工程》.
  147. 王晨阳，彭敏俊，夏庚磊，丛腾龙（2018）. 一体化压水堆非能动余热排出系统可靠性分析. 《哈尔滨工程大学学报》.
  148. Bowen Zhang, Minjun Peng, Shouyu Cheng, Lin Fu Sun (2018). Novel fuzzy logic based coordinated control for multi-unit small modular reactor. Annals of Nuclear Energy.DOI
  149. Nan Jiang, Tenglong Cong, Minjun Peng (2018). Margin evaluation of in-vessel melt retention for small IPWR. Progress in Nuclear Energy.DOI
  150. Wei Li, Minjun Peng, Qingzhong Wang (2018). Improved PCA method for sensor fault detection and isolation in a nuclear power plant. Nuclear Engineering and Technology.DOI
  151. Wei Li, Minjun Peng, Qingzhong Wang (2018). Fault identification in PCA method during sensor condition monitoring in a nuclear power plant. Annals of Nuclear Energy.DOI
  152. Tenglong Cong, Minjun Peng, Xiang Zhang (2018). Prediction of Subcooled Boiling With Uncertainties From Boundary Conditions and Interaction Models.DOI
  153. Meijie Gong, Minjun Peng, Haishan Zhu (2018). Research of Fast Modeling and Simulating Platform for Nuclear Power Plant Secondary Loop.DOI
  154. Yanan Zhao, Minjun Peng, Genglei Xia, Lianxin Lv (2018). Simulation Research on Thermal-Hydraulic Performance of a Natural Circulation Integrated Pressurized Water Reactor.DOI
  155. Yanan Zhao, Minjun Peng, Genglei Xia, Lianxin Lv (2018). Flashing-driven natural circulation characteristics analysis of a natural circulation integrated pressurized water reactor. Nuclear Engineering and Design.DOI
  156. Chenyang Wang, Genglei Xia, Tenglong Cong, Minjun Peng, Xing Lyu, Lin Fu Sun (2018). Operation characteristics analyses on a marine-type passive residual heat removal system. Annals of Nuclear Energy.DOI
  157. Wei Li, Minjun Peng, Qingzhong Wang (2018). Fault detectability analysis in PCA method during condition monitoring of sensors in a nuclear power plant. Annals of Nuclear Energy.DOI
  158. Meijie Gong, Minjun Peng, Haishan Zhu (2018). Research of multiple refined degree simulating and modeling for high pressure feed water heat exchanger in nuclear power plant. Applied Thermal Engineering.DOI
  159. Wei Li, Minjun Peng, Qingzhong Wang (2018). False alarm reducing in PCA method for sensor fault detection in a nuclear power plant. Annals of Nuclear Energy.DOI
  160. Nan Jiang, Minjun Peng, Tenglong Cong (2018). Simulation analysis of an open natural circulation for the passive residual heat removal in IPWR. Annals of Nuclear Energy.DOI
  161. Minjun Peng, Hang Wang, Shan-shan Chen, Geng-lei Xia, Yong-kuo Liu, Yang Xu, Abiodun Ayodeji (2018). An intelligent hybrid methodology of on-line system-level fault diagnosis for nuclear power plant. Nuclear Engineering and Technology.DOI
  162. Xiang Zhang, Ting Yu, Tenglong Cong, Minjun Peng (2018). Effects of interaction models on upward subcooled boiling flow in annulus. Progress in Nuclear Energy.DOI
  163. Wei Li, Minjun Peng, Yong-kuo Liu, Shouyu Cheng, Nan Jiang, Hang Wang (2018). Condition Monitoring of Sensors in a NPP Using Optimized PCA. Science and Technology of Nuclear Installations.DOI
  164. Nan Jiang, Minjun Peng, Wei Wei, Tenglong Cong (2018). Strategy Evaluation for Cavity Flooding during an ESBO Initiated Severe Accident. Science and Technology of Nuclear Installations.DOI
  165. 郭良壮，彭敏俊，王航，杨旭，李伟（2017）. 核电厂蒸汽旁排系统故障诊断与状态预测方法研究. 《中国核科学技术进展报告（第五卷）——中国核学会2017年学术年会论文集第10册（核测试与分析分卷、核安全分卷）》.
  166. 郑勇，彭敏俊（2017）. 基于CSG和OpenMP的复杂几何输运计算程序开发及验证. 《核动力工程》.
  167. 王冰，彭敏俊，夏庚磊，孙林，赵亚楠（2017）. 倾斜与摇摆条件下一体化反应堆自然循环特性研究. 《原子能科学技术》.
  168. 武茂浦，刘永阔，于巍峰，彭敏俊，周文，刘鹏飞（2017）. 基于BP-SDG的核动力装置典型故障诊断研究. 《中国核学会2017年学术年会》.
  169. 韩苗苗，郭智荣，刘海峰，李清华，彭敏俊，代传波（2017）. 边界体素处理方式对层析γ扫描技术的透射重建质量的影响. 《原子能科学技术》.
  170. Tenglong Cong, Minjun Peng, Zhijian Zhang (2017). Preliminary applications of CFD methodology on analysis of the single-phase laminar natural circulation under swing conditions. Progress in Nuclear Energy.DOI
  171. Tenglong Cong, Minjun Peng, Zhijian Zhang (2017). STUDY ON THE NATURAL CIRCULATION UNDER ROLLING CONDITION BY USING CFD METHODOLOGY. Proceeding of Second Thermal and Fluids Engineering Conference.DOI
  172. Wei Li, Minjun Peng, Yong-kuo Liu, Nan Jiang, Hang Wang, Zhiyong Duan (2017). Fault detection, identification and reconstruction of sensors in nuclear power plant with optimized PCA method. Annals of Nuclear Energy.DOI
  173. Yong Jiang Zheng, Minjun Peng (2017). Track truncation method for improving the computational efficiency of 2D matrix MOC. Annals of Nuclear Energy.DOI
  174. Genglei Xia, Yuan Yuan, Minjun Peng, Xing Lv, Lin Fu Sun (2017). Numerical studies of a helical coil once-through steam generator. Annals of Nuclear Energy.DOI
  175. Lihui He, Bing Wang, Genglei Xia, Minjun Peng (2017). Study on natural circulation characteristics of an IPWR under inclined and rolling condition. Nuclear Engineering and Design.DOI
  176. Yong-kuo Liu, Abiodun Ayodeji, Zhibin Wen, Wu Mao-pu, Peng Minjun, Yu Wei-feng (2017). A cascade intelligent fault diagnostic technique for nuclear power plants. Journal of Nuclear Science and Technology.DOI
  177. Li Ren, Peng Minjun, Xia Genglei, Zhao Yanan (2017). Research on Natural Circulation Flow Characteristics of Floating Nuclear Power Plant in Heaving Motion.DOI
  178. 吴国华，刘永阔，谢春丽，彭敏俊，段智勇（2016）. 基于SDG-QTA的核动力装置故障诊断技术研究. 《原子能科学技术》.
  179. 温志斌，刘永阔，段智勇，彭敏俊（2016）. PCA-SDG在反应堆冷却剂系统典型故障诊断中的应用. 《计算》.
  180. Yong Jiang Zheng, Minjun Peng, Genglei Xia (2016). Development and verification of MOC code based on Krylov subspace and efficient preconditioning techniques. Annals of Nuclear Energy.DOI
  181. Lin Fu Sun, Minjun Peng, Genglei Xia, Xing Lv, Li Ren (2016). Numerical Study on Coolant Flow Distribution at the Core Inlet for an Integral Pressurized Water Reactor. Nuclear Engineering and Technology.DOI
  182. Genglei Xia, G.H. Su, Minjun Peng (2016). Analysis of flow distribution instability in parallel thin rectangular multi-channel system. Nuclear Engineering and Design.DOI
  183. Xing Lv, Minjun Peng, Xiao Liang Yuan, Genglei Xia (2016). Design and analysis of a new passive residual heat removal system. Nuclear Engineering and Design.DOI
  184. Yong-kuo Liu, Meng-kun Li, Minjun Peng, Chun-li Xie, Cheng-qian Yuan, Shuang-yu Wang, Nan Chao (2016). Walking path-planning method for multiple radiation areas. Annals of Nuclear Energy.DOI
  185. Genglei Xia, G.H. Su, Minjun Peng (2016). Analysis of flow distribution in plate-type core affected by uneven inlet temperature distribution. Annals of Nuclear Energy.DOI
  186. Genglei Xia, G.H. Su, Minjun Peng (2016). Analysis of natural circulation operational characteristics for integrated pressurized water reactor. Annals of Nuclear Energy.DOI
  187. 雷世雄，徐非，谭翔，彭敏俊（2015）. 分布式策略的核动力装置故障诊断技术研究. 《计算》.
  188. 成守宇，李程，彭敏俊，刘新凯（2015）. 基于人工免疫的直流蒸汽发生器压力控制研究. 《核动力工程》.
  189. 晁楠，刘永阔，李梦堃，彭敏俊，王双宇，袁成前（2015）. 核设施退役场景的仿真实现技术研究. 《计算》.
  190. 孙英杰，彭敏俊（2015）. 基于MSET和SPRT的核动力装置异常状态监测技术研究. 《核动力工程》.
  191. 孙英杰，彭敏俊（2015）. 基于Simulink的变频电动机仿真. 《煤矿机械》.
  192. Hang Wang, Minjun Peng, Peng Wu, Shouyu Cheng (2015). Improved methods of online monitoring and prediction in condensate and feed water system of nuclear power plant. Annals of Nuclear Energy.DOI
  193. Yong-kuo Liu, Fei Xie, Chunli Xie, Minjun Peng, Guohua Wu, Hong Xia (2015). Prediction of time series of NPP operating parameters using dynamic model based on BP neural network. Annals of Nuclear Energy.DOI
  194. 袁媛，彭敏俊，夏庚磊，吕星（2014）. 螺旋管式直流蒸汽发生器热工水力分析模型. 《原子能科学技术》.
  195. 郑勇，彭敏俊，夏庚磊，刘新凯（2014）. 压水堆核电站堆芯物理/热工水力耦合特性研究. 《原子能科学技术》.
  196. 冯可新，彭敏俊，徐宇翔，刘新凯（2014）. 核电站给水加热器建模仿真. 《原子能科学技术》.
  197. 吴鹏，刘新凯，彭敏俊（2014）. 核电站凝汽器仿真模型研究. 《原子能科学技术》.
  198. 陈五星，夏庚磊，彭敏俊（2014）. 中国实验快堆主冷却系统建模与仿真研究. 《核动力工程》.
  199. 袁潇，彭敏俊，夏庚磊，刘新凯（2014）. 一种非能动余热排出系统设计方案. 《核动力工程》.
  200. 成守宇，彭敏俊，刘新凯（2014）. 免疫P-PID串级控制的核反应堆功率调节器研究. 《核动力工程》.
  201. 成守宇，彭敏俊，薛若军，赵强（2014）. 基于Topmeret的核电厂凝给水系统仿真研究. 《2014第二届中国指挥控制大会论文集（上）》.
  202. 成守宇，彭敏俊，刘新凯，赵强，邓祥鑫（2014）. 基于数字化仪控技术的核动力装置协调控制器的设计. 《北京核学会第十届（2014年）核应用技术学术交流会论文集》.
  203. Lin Sun, Minjun Peng, Genglei Xia (2014). Study on Natural Circulation Transition Process for IP200. The 6th International Symposium on Symbiotic Nuclear Power Systems (ISSNP2014).
  204. Dali Yu, Minjun Peng, Zhongyi Wang (2014). CFD study on the supercritical carbon dioxide cooled pebble bed reactor. Nuclear Engineering and Design.DOI
  205. Genglei Xia, Minjun Peng, Xue Du (2014). Research of flow instability in OTSG under low load conditions. Annals of Nuclear Energy.DOI
  206. Genglei Xia, Minjun Peng, Xue Du (2014). Analysis of Two-Phase Flow Instability in Multi-Channel System.DOI
  207. Genglei Xia, Minjun Peng, Xue Du (2014). Calculation analysis on the natural circulation of a passive residual heat removal system for IPWR. Annals of Nuclear Energy.DOI
  208. Dali Yu, Minjun Peng, Genglei Xia, Wanchao Mao, Yang Yang (2014). An evaluation of designed Start-up System (SUS) for once-through steam generators. Annals of Nuclear Energy.DOI
  209. 代守宝，彭敏俊，田兆斐，姜昊（2013）. 基于RELAP5的汽轮机仿真模型研究. 《原子能科学技术》.
  210. 郝承明，付文，彭敏俊，夏庚磊（2013）. 一体化反应堆强迫循环转自然循环过程瞬态特性分析. 《原子能科学技术》.
  211. 陈志辉，夏虹，邬芝胜，邓礼平，黄伟，彭敏俊，黄华（2013）. 小波变换在突变信号识别中的应用. 《核动力工程》.
  212. 成守宇，彭敏俊，赵强，邓祥鑫（2013）. 多堆核动力装置控制策略仿真研究. 《兵工自动化》.
  213. Salah Ud‐Din Khan, Shahab Ud‐Din Khan, Minjun Peng (2013). Flow blockage accident or loss of flow accident by using comparative approach of NK/TH coupling codes and RELAP5 code. Annals of Nuclear Energy.DOI
  214. Xiao Liang Yuan, Minjun Peng, Genglei Xia (2013). Nuclear Power Plant Passive Residual Heat Removal System Design and Simulation.DOI
  215. Yong-kuo Liu, Peng Minjun, Chun-li Xie, Dong Ya-xin (2013). Research and design of distributed fault diagnosis system in nuclear power plant. Progress in Nuclear Energy.DOI
  216. Xia Genglei, Peng Minjun, Xue Du (2013). Analysis of load-following characteristics for an integrated pressurized water reactor. International Journal of Energy Research.DOI
  217. 夏虹，陈志辉，邓礼平，黄华，彭敏俊（2012）. 基于小波的突变信号识别方法及应用研究. 《原子能科学技术》.
  218. 夏庚磊，郭赟，彭敏俊（2012）. 平行通道密度波不稳定性研究. 《原子能科学技术》.
  219. 蒋立国，彭敏俊，刘建阁，郭赟（2012）. 传热管破裂位置及根数对SGTR事故进程的影响. 《核科学与工程》.
  220. 王少武，夏庚磊，彭敏俊，方成跃（2012）. 平行通道流动不稳定性研究. 《原子能科学技术》.
  221. 刘新凯，刘建阁，彭敏俊（2012）. 基于RELAP5程序的直管式直流蒸汽发生器敏感性分析. 《原子能科学技术》.
  222. 蒋立国，彭敏俊，郭赟，刘建阁（2012）. 直流蒸汽发生器传热管破裂事故分析. 《原子能科学技术》.
  223. Salah Ud‐Din Khan, Salah Ud‐Din Khan, Minjun Peng, Lei Li, Shahab Ud‐Din Khan, Shahab Ud‐Din Khan (2012). Modification and validation of THEATRe code for the plate type fuel nuclear reactor. Annals of Nuclear Energy.DOI
  224. Salah Ud‐Din Khan, Salah Ud-Din Khan, Minjun Peng, Shahab Ud‐Din Khan, Shahab Ud‐Din Khan (2012). Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor. International Journal of Energy Research.DOI
  225. Xiaolong Sun, Minjun Peng, Genglei Xia (2012). Thermal-Hydraulic Character Effect Factors Analysis for Passive Residual Heat Removal System of Sodium-Cooled Fast Reactor.DOI
  226. Genglei Xia, Minjun Peng, Yun Rui Guo (2012). Research of two-phase flow instability in parallel narrow multi-channel system. Annals of Nuclear Energy.DOI
  227. Shaowu Wang, Chengyue Fang, Xia Genglei, Minjun Peng (2012). Analysis of instability in parallel channel system. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
  228. Peng Minjun (2012). Sensitivity Analysis of Once-Through Steam Generator Based on RELAP5 Code. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
  229. 代守宝，彭敏俊（2011）. 一体化压水堆非能动余热排出系统运行特性影响因素分析. 《原子能科学技术》.
  230. 刘洪涛，彭敏俊，田兆斐，薛若军（2011）. 核电站给水加热器建模与仿真. 《计算》.
  231. 朱荣旭，彭敏俊，巩诚（2011）. 核电厂分布式状态监测技术研究. 《中国核科学技术进展报告（第二卷）——中国核学会2011年学术年会论文集第3册（核能动力分卷（下））》.
  232. 郝承明，刘新凯，彭敏俊，夏庚磊，刘建阁（2011）. 直流蒸汽发生器分组运行对流动不稳定的影响. 《原子能科学技术》.
  233. 夏庚磊，董化平，彭敏俊，郭赟（2011）. 环隙窄缝通道管间脉动不稳定性分析. 《原子能科学技术》.
  234. 刘中坤，彭敏俊，朱海山，成守宇，巩诚（2011）. 核设施退役虚拟仿真系统框架研究. 《原子能科学技术》.
  235. Khan Salah Ud-Din, Minjun Peng, Muhammad Zubair (2011). Neutronics and Thermal Hydraulic Coupling Methods for the Nuclear Reactor Core. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  236. Salah Ud Din Khan, Minjun Peng, Shahab Ud Din Khan (2011). Thermal hydraulic analysis of small nuclear reactor core by using comparative approach of THEATRe and Relap5 code. International Journal of Nuclear Energy Science and Technology.DOI
  237. Peng Minjun (2011). Thermal-Hydraulic Characteristics Effect Factors Analysis for Passive Residual Heat Removal System of Integral Pressurized Water Reactor. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
  238. 刘中坤，彭敏俊，赵强（2010）. 核设施退役虚拟仿真中烟尘输运过程建模及算法研究. 《原子能科学技术》.
  239. 夏庚磊，郭赟，彭敏俊（2010）. 强迫循环并联通道流量漂移现象研究. 《原子能科学技术》.
  240. 王少武，彭敏俊，代守宝，成守宇，孙英杰（2010）. 基于RELAP5的船用核动力装置二回路数字模型. 《核动力工程》.
  241. 徐文奇，彭敏俊，刘建阁，蒋立国（2010）. 一体化压水堆双恒定运行方案控制策略研究. 《核科学与工程》.
  242. 田兆斐，赵强，彭敏俊，成守宇，薛若军（2010）. 自然循环与强迫循环转换过渡过程研究. 《哈尔滨工程大学学报》.
  243. 王盟，彭敏俊，孟祥男（2010）. 提高压水堆循环热效率的方案设计. 《计算》.
  244. 成守宇，王贺，彭敏俊，杨明，巩诚，刘飞（2010）. 核动力装置运行支持系统的设计与开发. 《核科学与工程》.
  245. 刘建阁，彭敏俊，张志俭，徐文奇，成守宇（2010）. 套管式直流蒸汽发生器负荷跟随动态特性分析. 《原子能科学技术》.
  246. 李明岩，彭敏俊，张志俭（2010）. 非能动核电站主给水丧失事故仿真研究. 《原子能科学技术》.
  247. 薛若军，邓程程，彭敏俊（2010）. 非能动余热排出热交换器数值模拟. 《原子能科学技术》.
  248. 夏庚磊，郭赟，彭敏俊（2010）. 基于RELAP5的两管平行通道流动不稳定性研究. 《原子能科学技术》.
  249. 代守宝，彭敏俊（2010）. IPWRs非能动余热排出系统运行特性分析. 《核科学与工程》.
  250. Shouyu Cheng, Minjun Peng, Cheng Gong, Xinkai Liu, XuanBo Lin (2010). Study and Development of Marine Power Station Simulator. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  251. Ruojun Xue, Chengcheng Deng, Minjun Peng (2010). Numerical Simulation Research of Natural Convection Heat Exchanger. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  252. Salah Ud‐Din Khan, Minjun Peng, Muhammad Zubair, Shaowu Wang (2010). A Review on Specific Features of Small and Medium Sized Nuclear Power Plants. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  253. Liguo Jiang, Minjun Peng, Jiange Liu (2010). Evaluation of a SGTR Accident in the Multi-Application Integrated Pressurized Water Reactor. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  254. Shouyu Cheng, Minjun Peng, Cheng Gong, Qiang Zhao, Zhaofei Tian, Haishan Zhu, Zhongkun Liu (2010). Research on Digital Control System Simulation for Nuclear Power Plants. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  255. Jiange Liu, Minjun Peng, Zhijian Zhang, Liguo Jiang (2010). Small-Break Loss of Coolant Accident Analysis of the Integrated Pressurized Water Reactor. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  256. Salah Ud‐Din Khan, Minjun Peng, Jiange Liu (2010). A Review: Activities in the Field of Small and Medium Sized Nuclear Power Plants. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  257. Minjun Peng (2010). Flow Excursion Instability in Forced Circulation Parallel Channels. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
  258. Shouyu Cheng, Minjun Peng, Zhaofei Tian, Qiang Zhao, Ruojun Xue (2010). Study on Control of Natural Circulation and Forced Circulation in Nuclear Power Plant. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  259. Shengyuan Yan, Kun Yu, Zhijian Zhang, Minjun Peng (2010). Simulation Based Multi-experts Evaluation Method for Human-machine Interface Design of Main Control Room. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  260. Liguo Jiang, Minjun Peng, Jiange Liu (2010). Preliminary Safety Analysis for Total Loss of Feedwater of the Multi-application Integrated Pressurized Water Reactor. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  261. Shoubao Dai, Minjun Peng (2010). Safety Analysis for IPWR under Over-Pressurizing Accident Conditions. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  262. Xuhua Ye, Minjun Peng, Jiange Liu (2010). Analysis of PRHRS for an Integral Pressurized Water Reactor Using RELAP5/MOD3.4. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  263. Tian Zhaofei, Peng Minjun, Wang Kaichuan (2010). Design of Thermal Economy On-Line Analysis System of Nuclear Power Unit. International Symposium on Information Engineering and Electronic Commerce.DOI
  264. Zhongkun Liu, Peng Minjun, Qiang Zhao, Cheng Shouyu, Haishan Zhu (2010). Research on Model and Algorithm for Simulation of Smoke-dust in Nuclear Facilities Decommissioning Virtual Simulation. International Symposium on Information Engineering and Electronic Commerce.DOI
  265. Ruo-Jun Xue, Deng Cheng-cheng, Peng Minjun (2010). Numerical Simulation of Passive Residual Heat Removal Heat Exchanger. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
  266. Peng Minjun (2010). Investigation on Two-Phase Flow Instability in Parallel Channels Based on RELAP5 Code. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
  267. Peng Minjun (2010). Analysis on the thermal-hydraulic characteristics for passive residual heat removal system of IPWRs. Chinese Journal of Nuclear Science and Engineering.
  268. 闫修平，彭敏俊，成守宇（2009）. 分布式故障诊断策略及其在核电站中的应用. 《核动力工程》.
  269. 刘建阁，彭敏俊，蒋立国（2009）. 多用途一体化轻水堆初步设计方案和安全分析. 《原子能科学技术》.
  270. 李明岩，彭敏俊，张志俭（2009）. 核电站非能动余热排出系统误开事故仿真研究. 《计算》.
  271. 刘建阁，彭敏俊，张志俭，黎华（2009）. 套管式直流蒸汽发生器稳态特性分析. 《哈尔滨工程大学学报》.
  272. 彭敏俊（2009）. 船舶核动力装置. 《原子能》.
  273. Jiange Liu, Minjun Peng, Zhijian Zhang, Lei Li (2009). Concept Design of the Multi-Application Integrated Light Water Reactor and Normal Operation Analysis. Asia-Pacific Power and Energy Engineering Conference (APPEEC).DOI
  274. Shengyuan Yan, Chunyan Xia, Zhijian Zhang, Minjun Peng, Ming Yang (2009). Application of Virtual Reality in Evaluation and Optimization for Human Machine Interface.DOI
  275. Jiange Liu, Minjun Peng (2009). Evaluation of the Flow and Heat Transfer Characteristic in Vertical Narrow Annulus Channel Based on the RELAPSCDAPSIM/MOD3.4 Code.DOI
  276. Shoubao Dai, Minjun Peng, Jiange Liu (2009). Optimization and Analysis for Passive Residual Heat Removal System of an Integral Pressurized Water Reactor.DOI
  277. 刘飞，张志俭，彭敏俊（2008）. 核电厂应急操作规程系统的开发. 《核动力工程》.
  278. Ming Yang, Zhijian Zhang, Shengyuan Yan, Minjun Peng (2008). Design and Development of a Reliability Analysis Tool Based on Multilevel Flow Models. Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance.DOI
  279. Fei Liu, Zhijian Zhang, Minjun Peng (2008). Research on the Computerized Symptom-Oriented Procedures of Nuclear Power Plants. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.DOI
  280. Peng Minjun (2008). Development of Emergency Operation Procedure System for Nuclear Power Plants. Hedongli gongcheng.
  281. 颜声远，于晓洋，张志俭，彭敏俊，杨明（2007）. 基于RBF网络的显示设计主观评价方法. 《哈尔滨工程大学学报》.
  282. 刘飞，张志俭，彭敏俊（2007）. 核电厂计算机化规程系统开发. 《核动力工程》.
  283. 刘飞，张志俭，彭敏俊（2007）. 核电站计算机化规程显示技术分析. 《核科学与工程》.
  284. 宁新献，镇启明，杨颖策，杨明，彭敏俊（2007）. 混合故障诊断方法在核电厂在线仿真系统中的应用. 《中国核学会2007年学术年会论文摘要集》.
  285. 刘文学，陈士强，彭敏俊（2007）. 核电站主冷却剂系统在线预测仿真研究. 《中国核学会2007年学术年会》.
  286. 颜声远，于晓洋，张志俭，彭敏俊，杨明（2007）. 多仪表综合显示系统人机界面的虚拟评价研究. 《系统仿真学报》.DOI
  287. 刘飞，张喆，彭敏俊（2007）. 核电厂SGTR事故征兆导向规程开发. 《中国核学会2007年学术年会论文摘要集》.
  288. 颜声远，于晓洋，张志俭，彭敏俊，杨明（2007）. 基于RBF网络的虚拟仪表人机界面评价方法. 《系统仿真学报》.
  289. Shengyuan Yan, Xiaoyang Yu, Hongguo Zhang, Zhijian Zhang, Peng Minjun, Wang Shanling (2007). Research of Software User Interface Evaluation Method based on Subjective Expectation. International Conference on Mechatronics and Automation.DOI
  290. Peng Minjun (2007). Analysis on the technology of computerized procedures presenting for nuclear power plants. Chinese Journal of Nuclear Science and Engineering.
  291. Peng Minjun (2007). Development of Computerized Procedures System for Nuclear Power Plants. Hedongli gongcheng.
  292. 颜声远，张志俭，彭敏俊，刘红娟（2006）. 基于UG/Open的人机界面设计评价实时交互方法研究. 《人类工效学》.
  293. Ming Yang, Z. J. Zhang, Minjun Peng, Shengyuan Yan, Hong Wang, J. Ouyang (2006). A Study on a Hybrid Approach for Diagnosing Faults in Nuclear Power Plant. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management.DOI
  294. Fei Liu, Zhang Zhijian, Peng Minjun (2006). Study of on-line computerized procedures system of nuclear power plants.
  295. Ming Yang, Jianfei Li, Peng Minjun, Shengyuan Yan, Zhijian Zhang (2006). A Hybrid Approach for Fault Diagnosis based on Multilevel Flow Models and Artificial Neural Network.DOI
  296. 颜声远，张志俭，彭敏俊，许彧青（2005）. 人机界面设计评价的实时交互方法. 《哈尔滨工程大学学报》.
  297. 彭敏俊（2005）. 船用核动力装置双恒定运行方案控制策略研究. 《哈尔滨工程大学学报》.
  298. 颜声远，李庆芬，张志俭，彭敏俊（2005）. 基于灰色理论的人机界面主观评价方法. 《哈尔滨工程大学学报》.
  299. Peng Minjun (2005). Research on control strategy of marine PWR nuclear power plant under ideal steady-state programming. Harbin Gongcheng Daxue Xuebao/Journal of Harbin Engineering University.
  300. 彭敏俊，杜泽（2001）. 船用压水堆核动力装置双恒定运行方案静态特性研究. 《核科学与工程》.
  301. 彭敏俊，杜泽（2001）. 船用压水堆核动力装置采用双恒定运行方案对总体运行性能的影响分析. 《哈尔滨工程大学学报》.
  302. 彭敏俊，黄渭堂，杜泽（2001）. 自然循环蒸汽发生器稳态运行特性实验研究. 《哈尔滨工程大学学报》.
  303. 彭敏俊，滕兵，张志华（2000）. 船用压水堆核动力装置双恒定运行方案下的冷却剂流量调节方案. 《哈尔滨工程大学学报》.
  304. 彭敏俊，杜泽，黄渭堂（1999）. 双恒定运行方式下主冷却剂系统稳定工况水力分析. 《哈尔滨工程大学学报》.
  305. 彭敏俊，杜泽，黄渭堂（1998）. 船用核蒸汽发生装置稳态运行特性研究. 《哈尔滨工程大学学报》.
  306. 彭敏俊，杜泽，滕兵（1998）. 船用核动力装置稳态运行方式探讨. 《核科学与工程》.
  307. 彭敏俊，王兆祥，杜泽，孙中宁（1997）. 船舶核动力装置人机系统设计研究. 《核动力工程》.
  308. 高璞珍，王兆祥，庞凤阁，丁洪河，彭敏俊，许岷（1997）. 摇摆情况下水的自然循环临界热流密度实验研究. 《哈尔滨工程大学学报》.
  309. 高璞珍，王兆祥，庞凤阁，丁洪河，彭敏俊，许岷（1997）. 两种管长单管中水临界热流密度(CHF)实验比较. 《哈尔滨工程大学学报》.
  310. 彭敏俊，黄渭堂，杜泽（1997）. 双恒定运行方式下船用压水堆的稳态热工安全分析. 《哈尔滨工程大学学报》.
  311. 高璞珍，庞凤阁，刘殊一，彭敏俊（1997）. 倾斜对强迫循环和自然循环影响的比较. 《核科学与工程》.
  312. 孙中宁，彭敏俊，杜泽，黄渭堂（1997）. 换热器热工计算中传热温差计算方法的一致性问题. 《核动力工程》.
  313. Hao-Wei Wang, Xingfu Cai, Minjun Peng, Miao Yang, Hongyi Yao. A fast and high-precision gamma-ray buildup factor prediction model based on ensemble machine learning. Annals of Nuclear Energy.DOI

预印本

  1. Yuchen Niu, Hanxing Liu, Minyun Liu, Le Ma, Yu Tang, Bitan Qin, Weiguang Wang, Zhenjiang Yu, Linwei Hu, Yuandong Zhang, Chenyang Wang, Minjun Peng, Houjun Gong, Yanping Huang (2026). Analysis of Start-up Operation Characteristics for a TAC based S-CO 2 Brayton Power Cycle. SSRN Electronic Journal.DOI
  2. Yiming Xiong, Minjun Peng, Genglei Xia, Yuandong Zhang, Ren Li (2026). Research on Core Design of Lead-Bismuth Reactors for Marine Nuclear Power and Comparative Study on the Performance of UO2 and UN Fuels. SSRN Electronic Journal.DOI
  3. Yuchen Niu, Zhanhao Zhang, Haiyang Zhang, Minyun Liu, Yuandong Zhang, Minjun Peng, Genglei Xia (2026). Control Strategy and Optimization Study of a TAC Configured S-CO₂ Reactor System. SSRN Electronic Journal.DOI
  4. Hang Wang, Chen Li, Yan Cui, Minjun Peng, Qiang Deng (2024). Intelligent Capsule Network and Feature Transfer for Fault Diagnosis in Nuclear Power Plant Rotating Machinery. SSRN Electronic Journal.DOI

书籍章节

  1. Minjun Peng, Zhaofei Tian, Genglei Xia, Hao Wang (2025). Thermal Cycle of NPPs. Nuclear science and technology.DOI
  2. Salah Ud‐Din Khan, Shahab Ud‐Din Khan, Minjun Peng (2020). Nuclear power plant systems. Elsevier eBooks.DOI

研究方向

核科学技术计算机软件及计算机应用自动化技术

此主页由公开资料整理，尚未经学者本人认领。