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检索条件"机构=Science and Technology on Reactor system Design Technology Laboratory"
1275 条 记 录,以下是81-90 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
Development and Verification of a New Depletion, Activation and Radiation Source Term Calculation Code  23rd
Development and Verification of a New Depletion, Activation ...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Wen, Xingjian Zhai, Zian Tang, Songqian Tian, Chao Liu, Zhouyu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China Xi’an Jiaotong University Xi’anShaanxi China
Existing depletion and source term calculation codes lack flexible interfaces, which is difficult to meet the actual engineering design needs. Based on the Chebyshev rational approximation method, a new depletion, act... 详细信息
来源: 评论
STUDY ON HYDROGEN RISK VENTING MITIGATION MEASURE OF SMALL STEEL CONTAINMENT DURING SEVERE ACCIDENT  29
STUDY ON HYDROGEN RISK VENTING MITIGATION MEASURE OF SMALL S...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Zou, Zhiqiang Zhang, Hang Zhang, Ming Peng, Huanhuan Xu, Youyou Deng, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The hydrogen risk in small steel containment is one of the most important safety problems of small modular reactor (SMR), effective measures need to be taken to mitigate the risk of high concentration hydrogen in a sm... 详细信息
来源: 评论
SGTR ANALYSIS OFSMR ONCE-THROUGH STEAM GENERATOR  29
SGTR ANALYSIS OFSMR ONCE-THROUGH STEAM GENERATOR
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Zhu, Ye Xiang, Cheng Wei, Liu Zhiyun, Cai Yun, Ren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The steam generator tube rupture (SGTR) of a nuclear power plant is a transient that is subject to numerous studies. The casing once-through steam generator has great heat-transfer capacity due to its dual-layer heat ... 详细信息
来源: 评论
Determination of Hardware Logic Drawing Simulation Modeling Criteria and Its Application in Nuclear Safety-Class DCS  6th
Determination of Hardware Logic Drawing Simulation Modeling ...
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6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021
作者: Zhang, Xu Chen, Shi-Yong Yao, Zhang Deng, Zhi-Guang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In digital control system (DCS) design, independent hardware logic circuit design is usually used to deal with common causes failures of software. Due to the distinct difference between the design criteria of electric... 详细信息
来源: 评论
DATA DRIVEN METHODS FOR BREAK SIZE AND LOCATION ESTIMATION IN LOCA BASED ON DEEP LEARNING  29
DATA DRIVEN METHODS FOR BREAK SIZE AND LOCATION ESTIMATION I...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Yuan, Peng Deng, Jian Qiu, Zhifang Zhu, Dahuan Huang, Tao Li, Zhongchun Du, Peng Xu, Qinglan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Loss of coolant accident (LOCA) is one of the most important accidents in thermal hydraulic design of nuclear power plant. The traditional analysis method is difficult to realize the rapid prediction of the size and l... 详细信息
来源: 评论
COMPARISON OF NUMERICAL ANALYSIS METHODS OF COOLANT ENVIRONMENTAL FATIGUE BASED ON STRAIN RATE CONTROL  29
COMPARISON OF NUMERICAL ANALYSIS METHODS OF COOLANT ENVIRONM...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Shao, Xuejiao Xie, Hai Zhang, Yixiong Xiong, Furui Wang, Xinjun Shi, Kaikai Yu, Mingda Huang, Xuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In this paper, the transformed strain rate of environmental fatigue correction factor (Fen), which is used to consider the influence of PWR primary coolant environment on material fatigue, is studied. EPRI's guide... 详细信息
来源: 评论
EVALUATION OF THE PARAMETER IMPORTANCE CHANGES OVER TIME FOR NUCLEAR reactor TRANSIENTS  29
EVALUATION OF THE PARAMETER IMPORTANCE CHANGES OVER TIME FOR...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Xiong, Qingwen Song, Gongle Du, Peng Huang, Tao Deng, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The uncertainty analysis and sensitivity analysis are two important parts in the safety analysis of nuclear reactor accidents, and the main purpose of the sensitivity analysis is to quantify the importance of the inpu... 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
STUDY ON STEADY OPERATIONAL CHARACTERISTICS OF FLOATING NUCLEAR reactor UNDER OCEAN CONDITION  29
STUDY ON STEADY OPERATIONAL CHARACTERISTICS OF FLOATING NUCL...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Cheng, Kun Chu, Xiao Qiu, Zhifang Xian, Lin Deng, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Different from land-based reactors, floating reactors are affected by the ocean condition. Numerical simulation is conducted to study the effects of heaving and rolling motion on typical floating nuclear reactor (FNR)... 详细信息
来源: 评论