百晓学者学者目录

林萌

上海交通大学核科学与工程学院

精选作品

期刊论文

  1. 林萌，李佳姝，金雅琪，黄轲（2026）. 氦氙空间堆入口温度及功率控制逻辑瞬态分析. 《核动力工程》.
  2. 王金培，林萌，李延凯，杨宗伟，赵锋（2026）. 基于快速非支配排序遗传算法的核电厂热工模型稳态参数智能优化研究. 《核科学与工程》.DOI
  3. 牛振锋，于爱民，李江宽，徐教珅，林萌，张泰熙，谭思超，田瑞峰（2026）. 基于量程特征缩放的核电厂智能故障诊断方法泛化性能增强. 《哈尔滨工程大学学报》.
  4. 赵冉，林萌，贺军，黄仕龙，林俊义（2025）. 基于RELAP5和Simulink的核电汽轮发电机组耦合仿真研究. 《核科学与工程》.DOI
  5. 金雅琪，林萌，丛源岐，肖凯，贺军，原伟超，李延凯（2025）. 紧凑型核动力系统负荷突加突卸工况控制系统优化. 《核科学与工程》.DOI
  6. 曹曦，林萌（2025）. 基于ABM的自适应步长求解点堆动力学方程. 《计算机仿真》.
  7. 陈逸龙，林萌，周士祺（2025）. 基于循环神经网络的核电厂复合故障诊断方法. 《海军工程大学学报》.
  8. 丛源岐，姜旭辉，林萌，杨燕华（2025）. 基于RELAP5的铅铋物性及传热模型改造研究. 《计算机仿真》.
  9. Jiangkuan Li, Shu-xin Zheng, Jiaoshen Xu, Meng Lin, Zhenfeng Niu, Jiahao Cheng, Chenxin Zhu, Ruifeng Tian, Sichao Tan (2025). Data augmentation-based fault diagnosis framework for nuclear power plants with robust anti-data interference capability. Annals of Nuclear Energy.DOI
  10. Shiqi Zhou, Meng Lin, Jun He, Yue Wu, Xu Wang (2025). Unsupervised clustering research of nuclear power plants under unlabeled unknown fault diagnosis scenario. Energy.DOI
  11. Shiqi Zhou, Meng Lin, Shilong Huang, Kai Xiao (2024). Open set compound fault recognition method for nuclear power plant based on label mask weighted prototype learning. Applied Energy.DOI
  12. 沈梦思，林萌（2023）. 相界面浓度输运方程在一维两流体模型中的应用研究. 《核动力工程》.
  13. Jiangkuan Li, Meng Lin, Bo Wang, Ruifeng Tian, Sichao Tan, Yankai Li, Junjie Chen (2023). Open set recognition fault diagnosis framework based on convolutional prototype learning network for nuclear power plants. Energy.DOI
  14. Meng Lin, Jiangkuan Li, Yankai Li, Xu Wang, Chengyi Jin, Junjie Chen (2023). Generalization analysis and improvement of CNN-based nuclear power plant fault diagnosis model under varying power levels. Energy.DOI
  15. Jiangkuan Li, Meng Lin, Yankai Li, Xu Wang (2022). Transfer learning network for nuclear power plant fault diagnosis with unlabeled data under varying operating conditions. Energy.DOI
  16. Jiangkuan Li, Meng Lin, Yankai Li, Xu Wang (2022). Transfer learning with limited labeled data for fault diagnosis in nuclear power plants. Nuclear Engineering and Design.DOI
  17. 曹瑛，沈梦思，林萌，常岩（2021）. MCCI过程中的化学反应模型研究. 《核科学与工程》.
  18. 李江宽，杨里平，林萌，景兴天（2021）. 用于控制系统现场调试的核电汽轮机仿真模型研究. 《核科学与工程》.
  19. 沈梦思，李羿良，林萌，肖凯（2021）. Simulink与CATIA的耦合仿真研究. 《核动力工程》.DOI
  20. 李江宽，黄涛，林萌，王旭，陈俊杰（2021）. 热工水力系统分析程序Courant条件计算方法研究. 《核动力工程》.DOI
  21. 李江宽，景兴天，林萌，陈俊杰，王治国（2021）. 反应堆热工水力系统分析程序时间步长控制方案研究. 《核动力工程》.DOI
  22. 郭英冉，李江宽，林萌，杨燕华，黄涛（2021）. 热工水力系统程序中数值水锤问题研究. 《核动力工程》.DOI
  23. 李江宽，林萌（2021）. 基于多数投票法的集成学习方法在核电厂故障诊断中的应用. 《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
  24. Ying Cao, Meng Lin, Mengsi Shen, Jiangkuan Li (2021). Research on the influence of chemical reaction model over MCCI heat transfer process. Annals of Nuclear Energy.DOI
  25. Jiangkuan Li, Meng Lin (2021). Research on robustness of five typical data-driven fault diagnosis models for nuclear power plants. Annals of Nuclear Energy.DOI
  26. Jiangkuan Li, Meng Lin (2021). Ensemble learning with diversified base models for fault diagnosis in nuclear power plants. Annals of Nuclear Energy.DOI
  27. Jiangkuan Li, Meng Lin (2021). Robustness Analysis and Improvement of Fault Diagnosis Model for Nuclear Power Plants Based on Random Forest.DOI
  28. Mengsi Shen, Meng Lin (2021). The Interfacial Area Weighted Area-Averaged Gas Velocity Model for the Interfacial Area Transport Equation in the System Analysis Code.DOI
  29. Yu‐Sheng Chen, Meng Lin, Ren Yu, Tianshu Wang (2021). Research on Simulation and State Prediction of Nuclear Power System Based on LSTM Neural Network. Science and Technology of Nuclear Installations.DOI
  30. 陈俊，沙会娥，吴照国，孔晓宁，尹铁男，林萌，杨燕华（2020）. 基于Newton-Raphson算法的COSINE热工水力程序安注箱模块研发. 《核科学与工程》.
  31. Zhao Xiumei, Meng Lin, Mengsi Shen, Hao Zhang, Yanhua Yang (2020). The application of the moving mesh method in a thermal hydraulic system code. Annals of Nuclear Energy.DOI
  32. Yankai Li, Xu Wang, Meng Lin (2020). Application of the dynamic FMEA in the reliability analysis of DCS. E3S Web of Conferences.DOI
  33. 赵秀梅，林萌，陈刚，杨燕华（2019）. 自适应网格加密在热工水力系统程序中的应用. 《核科学与工程》.
  34. 陈俊杰，赵秀梅，林萌，王旭，李延凯，陈纲（2019）. 核电厂全范围模拟机流固换热耦合并行技术研究. 《核动力工程》.
  35. 陈玉昇，杨燕华，林萌，余刃（2019）. 基于主元分析法的核反应堆关键参数提取研究. 《核动力工程》.
  36. 姚安宁，王苏，林萌，李延凯，王旭（2019）. 三维中子动力学程序cosKIND针对核电厂仿真应用的典型基准题验证. 《核科学与工程》.
  37. Ying Cao, Meng Lin, Mengsi Shen, LI Yan-kai, Yanhua Yang (2019). Research on code coupling method in severe accident simulator development. Annals of Nuclear Energy.DOI
  38. Mengsi Shen, Yu Lei, Meng Lin, Jianli Hao, Yiliang Li, Huang Ke, Kai Xiao (2019). Investigation on reverse flow phenomenon in UTSGs with abnormal secondary side water level under single-phase natural circulation. Progress in Nuclear Energy.DOI
  39. 曹瑛，赵秀梅，章雨，林萌（2018）. 基于堆芯模型耦合过渡方法的严重事故模拟机开发研究. 《核动力工程》.
  40. Zhao Xiumei, Ying Cao, Meng Lin, Hao Zhang, Yanhua Yang (2018). Adaptive mesh method applied to the thermal hydraulic program of system code with a judging criterion based on the matrix error. Annals of Nuclear Energy.DOI
  41. 周月善，钟明君，熊进标，林萌（2017）. 汽膜对熔滴水力学碎化影响的数值模拟. 《原子能科学技术》.
  42. 钟明君，周月善，林萌，熊进标，杨燕华（2017）. 基于界面跟踪与两流体模型的耦合模型对金属液柱碎化的数值模拟. 《核动力工程》.
  43. 陈俊，罗彬，吴照国，孔晓宁，林萌，杨燕华（2017）. COSINE子通道均相流分析程序的研发. 《核科学与工程》.
  44. Yankai Li, Meng Lin, Zongwei Yang, Yousheng Hou, Yanhua Yang (2017). Methods of applying nuclear simulation technology to the dynamic site testing of digital I&C system—I: Scheme of OLVT. Annals of Nuclear Energy.DOI
  45. Meng Lin, Yankai Li, Zongwei Yang, Yousheng Hou, Yanhua Yang (2017). Methods of applying nuclear simulation technology to the dynamic site testing of digital I&C system—Ⅱ: DCS-testing methods. Annals of Nuclear Energy.DOI
  46. Yankai Li, Zefeng Wang, Meng Lin, Mingjun Zhong, Yueshan Zhou, Yanhua Yang (2017). Experimental Studies on Breakup and Fragmentation Behavior of Molten Tin and Coolant Interaction. Science and Technology of Nuclear Installations.DOI
  47. Pengfeï Liu, Chunyu Bi, Yang Yu, Meng Lin, Xinli Song, Guoyang Wu, Zhida Su (2017). Development of a hardware-in- loop simulation platform for NPP main control systems. MATEC Web of Conferences.DOI
  48. 李美琳，林萌，杨燕华，张昊，龚湛（2015）. 应用于反应堆热工水力程序的核态沸腾传热关系式评价. 《核科学与工程》.
  49. 张荣金，李延凯，周源，林萌，杨燕华（2015）. 水滴与液态金属锡相互作用实验研究. 《核科学与工程》.
  50. 李治刚，钟明君，林萌，杨燕华（2015）. 核电厂直接安全壳加热事故的数值模拟与分析. 《核科学与工程》.
  51. Yankai Li, Meng Lin, Yanhua Yang (2015). Coupling methods for parallel running RELAPSim codes in nuclear power plant simulation. Nuclear Engineering and Design.DOI
  52. Daochuan Ge, Meng Lin, Yanhua Yang, Ruoxing Zhang, Qiang Chou (2015). Reliability analysis of complex dynamic fault trees based on an adapted K.D. Heidtmann algorithm. Proceedings of the Institution of Mechanical Engineers Part O Journal of Risk and Reliability.DOI
  53. Daochuan Ge, Dong Li, Meng Lin, Yanhua Yang (2015). SFRs-based numerical simulation for the reliability of highly-coupled DFTS. Eksploatacja i Niezawodnosc - Maintenance and Reliability.DOI
  54. YanKai Li, Meng Lin, Zefeng Wang (2015). ICONE23-1140 EXPERIMENTAL STUDIES ON FUEL COOLANT INTERACTIONS : PRIMARY RESULTS ANALYSIS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  55. 蔡溢，林萌，张昊，杨燕华（2014）. 反应堆热工安全分析程序相间摩擦模型开发测试. 《核技术》.
  56. 李延凯，林萌，杨燕华，刘斌（2014）. 核电厂仪控系统设计验证仿真平台开发. 《核动力工程》.
  57. 钟明君，林萌，张政铭，杨燕华（2014）. 基于1000 MW级压水堆核电厂压力容器外蒸汽爆炸的模拟研究. 《核动力工程》.
  58. Meng Lin, Mingjun Zhong, Yankai Li, Minghao Yuan, Yanhua Yang (2014). Numerical analysis on molten droplet hydrodynamic deformation and surface waves under high pressure pulse. Annals of Nuclear Energy.DOI
  59. Meng Lin, Yankai Li, Mingjun Zhong (2014). CHF prediction model research for flat and hypervapotron heating surface in subcooled flow nucleate boiling. Annals of Nuclear Energy.DOI
  60. Pengfeï Liu, Dong Hou, Meng Lin, Bo Kuang, Yanhua Yang (2014). Stability analysis of parallel-channel systems under supercritical pressure with heat exchanging. Annals of Nuclear Energy.DOI
  61. Zhigang Li, Jinghao Li, Meng Lin, Yanhua Yang (2014). Estimation of Ex-Vessel Steam Explosion Pressure Loads for AP1000 Nuclear Power Plant.DOI
  62. Mingjun Zhong, Meng Lin, Jinbiao Xiong, Yankai Li, Yanhua Yang (2014). Numerical Simulation of Thermal Behavior of a Molten Droplet Covered With Vapor Film.DOI
  63. Yuan Zhou, Meng Lin, Jin-bo Chen, Hanlin Wang (2014). Scaling analysis of thermal-hydraulics for steam generator passive heat removal system. Journal of Shanghai Jiaotong University (Science).DOI
  64. Mingjun Zhong, Yankai Li, Meng Lin, Minghao Yuan, Yanhua Yang (2014). A Numerical Analysis Research on Earlier Behavior of Molten Droplet Covered with Vapor Film at the Stage of Triggering and Propagation in Steam Explosion. Science and Technology of Nuclear Installations.DOI
  65. 雷蕾，林萌，周源，杨燕华（2013）. 蒸汽爆炸中熔融物液滴直径敏感性分析. 《核技术》.
  66. Mingjun Zhong, Yuan Zhou, Meng Lin, Minghao Yuan, Yanhua Yang (2013). Numerical simulation of molten droplet deformation and disintegration under sudden accelerations. Annals of Nuclear Energy.DOI
  67. Yuan Kang Zhou, Meng Lin, Mingjun Zhong, Yan Xiao, Yanhua Yang (2013). Molten metal and water direct contact interaction research – I. Photographic experiment study. Annals of Nuclear Energy.DOI
  68. Meng Lin, Yuan Zhou, Mingjun Zhong, Xiao Ke Yan, Yanhua Yang (2013). Molten metal and water direct contact interaction research – II. Numerical analysis. Annals of Nuclear Energy.DOI
  69. Yuan Zhou, Zhengming Zhang, Meng Lin, Hou Dong, Xiao Ke Yan (2013). Capability of RELAP5 MOD3.3 code to simulate density wave instability in parallel narrow rectangular channels. Annals of Nuclear Energy.DOI
  70. Yuan Zhou, Zhengming Zhang, Meng Lin, Minghao Yuan, Yan Xiao (2013). Numerical simulation of fragmentation of melt drop triggered by external pressure pulse in vapor explosions. Annals of Nuclear Energy.DOI
  71. 侯东，刘鹏飞，林萌，杨燕华（2012）. 加热通道内超临界流动的稳定性分析——频域分析. 《上海交通大学学报》.
  72. 熊义强，林萌，侯东，杨燕华（2012）. 多个两流体程序耦合的核电站系统热工水力建模及仿真研究. 《核科学与工程》.
  73. 熊义强，林萌，刘鹏飞，杨燕华（2012）. CPR1000型核电站给水泵事故瞬态分析. 《原子能科学技术》.
  74. Meng Lin, Peipei Chen (2012). Photographic study of bubble behavior in subcooled flow boiling using R-134a at low pressure range. Annals of Nuclear Energy.DOI
  75. Yuan Zhou, Meng Lin, Zhengming Zhang, Lei Lei (2012). Visual Experiments on the Subcooled Water Droplet Behavior in High Temperature Molten Metal.DOI
  76. 侯东，许志红，林萌，刘鹏飞，杨燕华（2011）. 垂直加热通道内超临界水流动稳定性参数敏感性分析. 《核科学与工程》.
  77. 侯东，林萌，杨宗伟，刘鹏飞，杨燕华（2011）. 核电厂DCS闭环测试平台的开发及应用. 《核动力工程》.
  78. Dong Hou, Meng Lin, Pengfeï Liu, Yanhua Yang (2011). Stability analysis of parallel-channel systems with forced flows under supercritical pressure. Annals of Nuclear Energy.DOI
  79. 苏耿，林萌，杨燕华，侯东（2010）. 核电厂汽轮机详细数值建模研究及其瞬态分析. 《核动力工程》.
  80. 许世杰，林萌，杨燕华，程旭（2010）. 基于核电站完整二回路的数学模型. 《核动力工程》.
  81. 朱立志，林萌，杨宗伟，刘鹏飞，杨燕华（2010）. 核电厂数字化仪表控制系统仿真测试平台开发. 《核动力工程》.
  82. Dong Hou, Meng Lin, Zhihong Xu, Yanhua Yang (2010). Development and application of an extensible engineering simulator for NPP DCS closed-loop test. Annals of Nuclear Energy.DOI
  83. Meng Lin, Dong Hou, Pengfeï Liu, Zongwei Yang, Yanhua Yang (2010). Main control system verification and validation of NPP digital I&C system based on engineering simulator. Nuclear Engineering and Design.DOI
  84. 林桦，林萌，侯东，杨燕华（2009）. 反应堆功率控制系统的建模及闭环验证. 《核动力工程》.
  85. 刘鹏飞，林萌，侯东，陈智，杨燕华（2009）. 核电厂DCS系统功能验证工程模拟机研究. 《核动力工程》.
  86. 杨宗伟，黄铁明，冯光宇，栾振华，林萌，朱立志（2009）. 核电站仿真技术在反应堆控制系统调试中的应用. 《核动力工程》.
  87. Meng Lin, Zongwei Yang, Dong Hou, Pengfeï Liu (2009). Applying Engineering Simulator to Verification and Validation of Digital I&C in Nuclear Power Plant.DOI
  88. 吴鹏，杨燕华，林萌（2008）. 稳压器安全阀卡开导致的堆芯熔化事故. 《核动力工程》.
  89. Meng Lin (2008). Study on Core Melting Accident Induced by One Stuck-Open Pressurizer Safety Valve. Hedongli gongcheng.
  90. 丁书华，杨燕华，朱学农，林萌（2007）. 先进压水堆核电厂保护系统需求分析的层次结构. 《原子能科学技术》.
  91. 高蕊，杨燕华，林萌（2007）. 基于系统程序的压水堆核电厂热力系统建模. 《核动力工程》.
  92. 侯东，林萌，许志红，杨燕华，陈智（2007）. 用Simulink扩展RELAP5的控制与保护系统仿真功能. 《核动力工程》.
  93. 林萌，陈玉清，张虹，刘定明，杨燕华（2007）. RELAP5堆芯功率计算模型的扩展. 《核动力工程》.
  94. Gao Rui, Yanhua Yang, Meng Lin, Yuan Ming-hao, Xie Zheng-rui (2007). ICONE15-10411 INVESTIGATION OF MODELING AND SIMULATION ON A PWR POWER CONVERSION SYSTEM WITH RELAP5. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  95. Meng Lin (2007). Modeling on a PWR Power Conversion System with System Program. Hedongli gongcheng.
  96. 胡锐，杨燕华，林萌，张荣华（2006）. 核电站控制保护及辅助系统仿真方法研究. 《核动力工程》.
  97. 徐珍，杨燕华，林萌，杨晓（2006）. 反应堆热工分析程序中可视化建模技术应用. 《核动力工程》.
  98. Meng Lin, Dong Hou, Zhihong Xu, Yanhua Yang, Ronghua Zhang (2006). System Simulation of Nuclear Power Plant by Coupling RELAP5 and Matlab/Simulink.DOI
  99. 林萌，杨燕华，胡锐，苏云，张荣华（2005）. RELAP5作为核电站模拟器热工水力系统程序的改造. 《核动力工程》.
  100. 林萌，苏云，胡锐，杨燕华（2005）. 核电站工程模拟器用于SGTR事故仿真分析研究. 《原子能科学技术》.
  101. 林萌，苏云，胡锐，杨燕华（2005）. 核电站工程模拟器中的RELAP5建模. 《原子能科学技术》.
  102. 林萌，胡锐，杨燕华（2004）. 核电厂控制与保护系统动态仿真. 《核动力工程》.
  103. Meng Lin, Yun Su, Rui Sheng Hu, Ronghua Zhang, Yanhua Yang (2004). Development of a thermal–hydraulic system code for simulators based on RELAP5 code. Nuclear Engineering and Design.DOI

研究方向

核科学技术计算机软件及计算机应用生物学

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