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会议文集


文集名Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle
会议名31st International Conference on Nuclear Engineering (ICONE31)
中译名《第三十一届国际核工程会议，卷1》
机构American Society of Mechanical Engineers (ASME)
会议日期4-8 August 2024
会议地点Prague, Czech Republic
出版年2024
馆藏号354060


题名作者出版年
EVALUATION OF COMPONENT COOLING SYSTEM BASED ON OPTIMIZATION ALGORITHM IN HPR1000PeiYu; Hou Ting; Yaguang Liu2024
RISK ASSESSMENT OF THE INTEGRATION OF A LARGE-SCALE HYDROGEN COGENERATION FACILITY INTO A VVER POWER PLANTEduard Diaz-Pescador; Marco Viebach; Florian Gamaleja; Antonio Hurtado2024
PRELIMINARY STUDY ON ENDOSCOPIC ULTRASOUND SYSTEM FOR IN-SERVICE INSPECTION OF HELICAL TUBE ONCE-THROUGH STEAM GENERATORZe Xi; Xiangang Wang; Xiaowei Luo; Junjie Zhou; Lei Song2024
ECONOMICAL RESEARCH ON HYDROGEN PRODUCTION OF SODIUM-COOLED FAST REACTORZhiwen Dai2024
FINITE ELEMENT ANALYSIS OF RUPTURE PRESSURE OF ALLOY 690 STREAM GENERATOR TUBES WITH DEFECTSZhang Bin; Jiang Nai-bin2024
DHP: CLOUD-EDGE COLLABORATIVE INTERNET FRAMEWORK FOR NUCLEAR POWER INDUSTRYMinmin Cheng; Yingang Jing; Kui Xu; Xianying Liu2024
MACHINE LEARNING APPROACH TO ANALYZING DATA IN JAPANESE BWR CHEMISTRY DATABASEGaku Yamazaki2024
A BRIEF INTRODUCTION TO SEVERAL IMPORTANT DESIGN OPTIMIZATIONS OF PASSIVE NUCLEAR POWER PLANTS IN CHINABaisong Ma; Zhengqiang Miao; Yuanhua Ma2024
INVESTIGATION ABOUT CLASSIFICATION OF STRESSES DUE TO RADIAL DEFORMATION INDUCED BY DESIGN PRESSURE APPLIED TO THE TUBES OF SQUARE PITCH MULTI-PERFORATED PORTION OF THICK PLATESP. Duranton; D. Jolly; M. Bernion; A. Benrabia; A. Amzil; T. Da Silva2024
STRESS INTENSITY FACTOR SOLUTIONS FOR CIRCUMFERENTIAL THROUGH-WALL CRACKS APPLICABLE TO POOL TYPE SODIUM COOLED FAST REACTORSHiroki Yada; Shigeru Takaya; Hideo Machida2024
RESEARCH ON ADAPTIVE UPDATING METHOD OF NUCLEAR POWER PLANT TRANSIENT MODELS BASED ON CONCEPT DRIFTJitao Li; Zijian Wu; Xiaojin Huang2024
DESIGN AND CALCULATION OF NUCLEAR HEATING SYSTEM UTILIZING A MOLTEN SALT HEAT STORAGE CIRCUIT FOR WASTE HEAT ABSORPTION AND PEAK REGULATIONHaofang Chong; Ruojun Xue; Sen Wang; Yaowu Cao; Furu Jing2024
ANALYSIS OF WATER HAMMER IN THE REACTOR COOLANT SYSTEM BASED ON WAVE TRACKING METHODQianping Zhang; Shubiao Dong; Xiaoyu Zhang2024
RESEARCH ON AUTOMATIC CABLE LAYOUT METHOD FOR NUCLEAR POWER PLANT BASED ON A* ALGORITHMHailong Du; Jie Cheng; Jianjun Wang; Puzhen Gao; Xuchen Deng; Kai Tang; Lei Wang; Jincheng Su2024
RESEARCH ON SEALING PERFORMANCE AND ELECTRICAL PERFORMANCE OF ELECTRICAL PENETRATION ASSEMBLY IN NUCLEAR REACTOR CONTAINMENTYanlu wang; Xinli Yu; Xiaxin Cao; Yu Liu2024
APPLICATION OF ARTIFICIAL NEURAL NETWORKS IN THE OPTIMIZATION OF FEEDWATER HEATER MODELSDong Shubiao; Zhang Xiaoyu; Zhang Qianping2024
RESEARCH ON INTERPRETABILITY TECHNIQUES IN TWO WIDELY USED NEURAL NETWORK FOR NUCLEAR POWER PLANT FAULT DIAGNOSISJie Liu; Rafael Macian-Juan2024
WAYS TO SOLVE THE SAFE OPERATION OF VVER-1000 REACTORS IN CASE OF LOSS OF ORIGINAL ROD CLUSTER CONTROL ASSEMBLIES SUPPLYOleksandr Mazurok; Vadym Ivanov; Valeriy Zuyok; Mykhaylo Tretyakov2024
KEY TECHNOLOGIES RESEARCH FOR THE IMPLEMENTATION OF IN-SERVICE INSPECTION STRATEGIES OPTIMIZING FOR THE REACTOR COOLANT SYSTEM OF IN-SERVICE NUCLEAR POWER PLANTSShen yunhai; Deng feng; Duan yongqiang; Yu xiaoquan; Ye shuixiang2024
REMOTE IMPACT ACOUSTIC INSPECTION OF STRUCTURES USING WATER JET IMPACTSSaeko Tokuomi; Kazuya Mori; Yasutaka Ohshima2024
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