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检索条件"机构=Science and Technology on Reactor System Design Technology Lab"
730 条 记 录,以下是31-40 订阅
design and Simulation Verification of Intelligent Perception and Adaptive Control system for Control Rod Drive Mechanism  30
Design and Simulation Verification of Intelligent Perception...
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30th International Conference on Nuclear Engineering, ICONE 2023
作者: Yang, Hui Lin, Yuanfeng Zeng, Hui Huang, Qingyu Zhang, Siyuan Yang, Kunlin Wang, Yuanmei Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Nuclear power plant status monitoring and equipment fault diagnosis are important guarantees for the safe operation of nuclear power plants. With the development of artificial intelligence technology, fault diagnosis ... 详细信息
来源: 评论
Anti-interference Study of Wireless Sensor Networks in Nuclear Power Plants  1
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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023
作者: Deng, Zhi-guang Wu, Qian Lv, Xin Xiang, Mei-qiong Xu, Tao Qin, Yue Sun, Yong-sheng Peng, Ye-shun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The compatibility and anti-interference capability of wireless sensor networks within nuclear power plants in complex electromagnetic environments are the most essential elements to ensure reliable operation and effec... 详细信息
来源: 评论
Research on Ultra High Flux Research reactor  23rd
Research on Ultra High Flux Research Reactor
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Zhang, Xue Yu, Hongxing Xia, Bangyang Li, Wenjie Zhang, Xilin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The lack of fast neutron irradiation test equipment is a key practical factor that restricts the development of the new generation nuclear energy technology with fast reactor as the core in China. Scarce isotopes such... 详细信息
来源: 评论
The Optimization design of the reactor Coolant system Based on Optimus  23rd
The Optimization Design of the Reactor Coolant System Based ...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Yanli, Yuan Xianhui, Ye Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
Structural dynamic analysis of reactor coolant systems is an important means of evaluating the safety of nuclear power plants under seismic loads. The seismic load distribution of the equipment can be obtained through... 详细信息
来源: 评论
Effect of Corrosion Damage on Structural Failure Models Under Different Boundry Conditions  23rd
Effect of Corrosion Damage on Structural Failure Models Unde...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Qian, Sheng Sun, Yu Huangfu, Yuzhao Zhang, Ke Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
Nuclear energy is an important means to deal with the energy crisis and global climate change, and the long-term safe operation of nuclear power plants strongly depends on the service behavior of structural materials.... 详细信息
来源: 评论
Research on Application of High Temperature and High Pressure Radar Liquid Level Measurement in Nuclear Power Plant  1
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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023
作者: Deng, Zhi-Guang Zhu, Bi-Wei Wu, Qian Wang, Xue-Mei Xu, Si-Jie Zhu, Jia-Liang Dong, Chen-Long Sun, Yong-Sheng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
At present, the water levels of high-temperature and high-pressure vessels such as voltage stabilizers and steam generators on ships' nuclear power plants are measured by the pressure principle. Affected by the lo... 详细信息
来源: 评论
Research on the Alarm Threshold for Steam Generator Tube Leak Monitoring of Small Modular reactor  23rd
Research on the Alarm Threshold for Steam Generator Tube Lea...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Xia, Ming-ming Wang, Jun-long Xu, Tao Huang, Bo-chen Zhu, Jian-ping Wu, Yi-rui Miao, Jian-xin Chen, Xin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sicuan Chengdu China
On the basis of fully learning from the existing principles of leak monitoring alarm thresholds setting of the steam generator tube in pressurized water reactor nuclear power plants, the principle of setting for N-16 ... 详细信息
来源: 评论
Prospects for Next Generation Nuclear Power system  23rd
Prospects for Next Generation Nuclear Power System
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Zhang, Yaoxiang Yu, Hongxing Xia, Bangyang Li, Wenjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
systematically research has been carried out on the demand of economic development for low-carbon clean energy and the opportunities faced by the development of nuclear power. A new generation of nuclear power technic... 详细信息
来源: 评论
Research and Application of Endogenous Security Active Defense technology for Domestic Nuclear Safety-Level Gateway Equipment  7th
Research and Application of Endogenous Security Active Defen...
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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023
作者: Li, Yong Liu, Ming-Xing Peng, Hao Hou, Rong-Bin Ma, Quan Wang, Ru-Qiao Liang, Gen-Hua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Gateway is a protective equipment at the boundary of the nuclear safety-level I&C system. Aiming at the unknown threat across the boundary of information physical space, this paper studies several key technologies... 详细信息
来源: 评论
SMR FEEDWATER system ANALYSIS  30
SMR FEEDWATER SYSTEM ANALYSIS
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30th International Conference on Nuclear Engineering, ICONE 2023
作者: Zhu, Ye Liang, Qiao Xianwei, Liao Zhiyun, Cai Minghao, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
The once through steam generator has great heat transfer capacity and compact structure. Some small module reactors (SMR) applied once through steam generatorfor its high thermal efficiency. The thermal hydraulic char... 详细信息
来源: 评论