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检索条件"机构=Science and Technology on Reactor System Design Technology Lab"
726 条 记 录,以下是101-110 订阅
排序:
A Novel Model for Dynamic Process Study of reactor Control Rod Drive Mechanism  26
A Novel Model for Dynamic Process Study of Reactor Control R...
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26th International Conference on Electrical Machines and systems, ICEMS 2023
作者: Yang, Yun Xu, Qiwei Zhang, Xuefeng Yu, Tianda Chen, Xinan Zhao, Yizhou Chongqing University National Key Laboratory of Power Transmission Equipment Technology Chongqing China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
The magnetic jack type control rod drive mechanism (CRDM) is a critical electromagnetic actuator utilized in reactors, with its movable components subject to the combined effects of electromagnetic force, liquid resis... 详细信息
来源: 评论
The Application of Different Distance Functions in DS Evidence Theory  5
The Application of Different Distance Functions in DS Eviden...
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5th IEEE International Conference on Electronics technology, ICET 2022
作者: Chen, Jie Li, Yiliang Zhao, Mengwei Huang, Ke Wu, Kunren Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China
DS evidence theory is a widely used uncertainty inference algorithm for decision fusion that can fuse this complementary and redundant information to reduce the uncertainty of the system. Evidence conflict is the most... 详细信息
来源: 评论
Preliminary Development of a Simulation Capability for Zircaloy Clad Ballooning in LOCA
Preliminary Development of a Simulation Capability for Zirca...
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International Conference on Water reactor Fuel Performance Meeting, WRFPM 2023
作者: Li, A. Wei Wu, B. Xiaoli State Key Laboratory for Strength and Vibration of Mechanical Structures Xi’an Jiaotong University Xi’an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Zircaloy clad is widely known to be vulnerable to ballooning and burst in a loss-of-coolant accident (LOCA) typical of high-temperature steam environment, due to internal and external pressure difference and degraded ... 详细信息
来源: 评论
Numerical Simulation of Flow Boiling Heat Transfer in Helical Tubes Under Marine Conditions  23rd
Numerical Simulation of Flow Boiling Heat Transfer in Helica...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Yuan, Leqi Cheng, Kun Bian, Haozhi Liao, Yaping Jiang, Chenxi Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Heilongjiang Harbin China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
Lead-based cooled reactors in most countries and some small reactors at sea use helical tube steam generators. Compared with U-tubes, the convection heat transfer coefficient in the spiral tube is higher, the structur... 详细信息
来源: 评论
Investigation on the Influence of Entrained Air to Internal Flow of Centrifugal Pumps under Cavitation Condition
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International Journal of Fluid Machinery and systems 2022年 第1期15卷 56-63页
作者: Fanjie, Deng Jianping, Yuan Song, Yang Biaobiao, Wang Qiaorui, Si Research Center of Fluid Machinery Engineering and Technology Jiangsu University Jiangsu Zhenjiang212013 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610000 China
The introduction of air is often used in engineering to delay the occurrence of cavitation. A steady simulation on a single-stage and single-suction centrifugal pump was used to study the influence of the air on the i... 详细信息
来源: 评论
Decoupling and Coupling Simulation Analysis in Small Nuclear Power Plant  23rd
Decoupling and Coupling Simulation Analysis in Small Nuclear...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Tian, Peiyu Li, Yi Xing, Tianyang Liang, Tiebo Wang, Changshuo Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China School of Energy and Environment Southeast University Jiangsu Nanjing China
As the development of computer science technology and the requirement of thorough research, more researchers are setting their eyes on coupling method because of the tight coupling in NPP (nuclear power plant) system.... 详细信息
来源: 评论
PREDICTION OF CRITICAL HEAT FLUX BASED ON RANDOM FOREST ALGORITHM  29
PREDICTION OF CRITICAL HEAT FLUX BASED ON RANDOM FOREST ALGO...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Sun, Zhuo Han, Mingyang Yuan, Peng Gong, Lei Chen, Di Yuan, Guanghui Zhang, Shuang Nuclear Power Institute of China Chengdu China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
The accurate prediction of critical heat flux(CHF) is of great significance to the safe operation of the reactor. At present, most of the traditional methods for predicting CHF are based on relational fitting in mathe... 详细信息
来源: 评论
Research on the application of Cobalt-Based Alloy Laser Additive Manufacturing in reactor Internals  29
Research on the application of Cobalt-Based Alloy Laser Addi...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Wang, Qingtian Cao, Rui Zhang, Xianjun Science and Technology on Reactor System Design Technology Laboratory Chengdu China Nuclear Power Institute of China Chengdu China
In view of the quality problems of manual TIG coating of cobalt-based alloy, the Laser Additive Manufacturing process was studied, especially the optimization of process parameters. Then a series of experiments were c... 详细信息
来源: 评论
INVESTIGATION ON THE SIMULATION OF TURBULENT HEAT TRANSFER OF LIQUID METAL FLOW IN A NARROW RECTANGULAR CHANNEL  29
INVESTIGATION ON THE SIMULATION OF TURBULENT HEAT TRANSFER O...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Zhang, Xue Yu, Hongxing Deng, Jian Du, Sijia Zhang, Xilin Zou, Ziqiang Feng, Wenpei Zhang, Yaoxiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Hefei China
Liquid metal has the advantages of high boiling point and strong thermal conductivity and is selected as the coolant for a new generation nuclear system. In addition, the narrow rectangular channel is used in the smal... 详细信息
来源: 评论
Phase-Field Modelling of Void Evolution in Binary Alloys Under Irradiation
Phase-Field Modelling of Void Evolution in Binary Alloys Und...
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International Conference on Water reactor Fuel Performance Meeting, WRFPM 2023
作者: Lu, Yong Yang, Yuhang Li, Wenjie Sun, Dan Liu, Xingjun Wang, Cuiping College of Materials and Fujian Key Laboratory of Surface and Interface Engineering for High Performance Materials Fujian Xiamen China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
The formation and growth of voids have significant influence on the dimensional changes of nuclear materials subjected to irradiation. In this paper, we developed a phase-field model to investigate the evolution of vo... 详细信息
来源: 评论