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检索条件"机构=Science Technology on Reactor System Design Technology Laboratory"
1282 条 记 录,以下是111-120 订阅
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
NUMERICAL INVESTIGATION ON THE THERMAL-HYDRAULIC AND FIV CHARACTERISTICS IN LBE-COOLED HELICAL CRUCIFORM FUEL AND WIRE-WRAPPED FUEL  31
NUMERICAL INVESTIGATION ON THE THERMAL-HYDRAULIC AND FIV CHA...
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2024 31st International Conference on Nuclear Engineering, ICONE 2024
作者: Qi, Zhang Haoyu, Wang Cao, Junxian Yuanming, Li Chenxi, Li Zhenhai, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The lead bismuth eutectic (LBE) cooled fast reactor in one of the General 4 advanced reactors, which plays significant role in the nuclear fuel cycle. In the recent years, the wire-wrapped fuel with four wires surroun... 详细信息
来源: 评论
Comparative study on thermal stress analysis and fatigue curve in stress and fatigue calculation of nuclear equipment  28
Comparative study on thermal stress analysis and fatigue cur...
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2021 28th International Conference on Nuclear Engineering, ICONE 2021
作者: Shao, Xuejiao Xie, Hai Yixiong, Y. Zhang, Liping Fu, Xiaolong Mi, Xue Li, Hui Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In the stress and fatigue evaluation of primary nuclear equipment, thermal stress calculation and fatigue curve have a great impact on the calculation results. There is a problem of stability in the step integral when... 详细信息
来源: 评论
Research on the effect of grid clamping failure on flow elastic stability and vortex shedding of fuel rod  26
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2018 26th International Conference on Nuclear Engineering, ICONE 2018
作者: Huan-Huan, Qi Zhi-Peng, Feng Nai-Bin, Jiang Qian, Huang Xuan, Huang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Flow elastic stability and vortex shedding were two important mechanisms of the flow induced vibration analysis. Due to the influence of manufacturing process, transportation and irradiation, the clamping action of gr... 详细信息
来源: 评论
POST-HOC INTERPRETABILITY BASED PARAMETER SELECTION FOR DATA ORIENTED NUCLEAR reactor ACCIDENT DIAGNOSIS system  29
POST-HOC INTERPRETABILITY BASED PARAMETER SELECTION FOR DATA...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Li, Chengyuan Li, Meifu Qiu, Zhifang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
During applying data-oriented diagnosis systems to distinguishing the type of and evaluating the severity of nuclear power plant initial events, it is of vital importance to decide which parameters to be used as the s... 详细信息
来源: 评论
Flow-induced vibration analysis of the check valve  25
Flow-induced vibration analysis of the check valve
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25th International Congress on Sound and Vibration 2018: Hiroshima Calling, ICSV 2018
作者: Shuai, Liu Peng, Feng Zhi Zhou, Jiang Xiao Xi, Lv Shou, Zhang Feng Xuan, Huang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
As an important over-current adjustment unit in the nuclear power plant piping system, check valve often causes some vibration and noise problems. The study of the existing valves mainly focuses on the simple or fixed... 详细信息
来源: 评论
Preliminary research on the thermal-mechanical coupling behavior simulation method of m3 fuel  28
Preliminary research on the thermal-mechanical coupling beha...
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2021 28th International Conference on Nuclear Engineering, ICONE 2021
作者: Changbing, Tang Yongjun, Jiao Yuanming, Li Kun, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institution of China Chengdu China
M3 fuel which microencapsulated TRISO particles in zirconium metal matrix is an integrated fuel designed to replace the traditional pellet-cladding fuel rod. The fuel design can effectively solve the problems of LWR f... 详细信息
来源: 评论
A new turbulent Prandtl number model for forced fully-developed pipe heat transfer of liquid metals  27
A new turbulent Prandtl number model for forced fully-develo...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Peiying, Li Hongxing, Yu Sijia, Du Yaou, Shen Mingyu, Yan Hongsheng, Yuan Yu, Liu Xiaoli, Wu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
With the proposal of liquid metals as coolant of the reactors, the use of accurate heat transfer correlation and reliable turbulent prandtl number(Prt)model of these low prandtl number fluids in turbulent flow is es... 详细信息
来源: 评论
STUDY ON DYNAMIC RESPONSE OF reactor CORE BARREL UNDER PUMP-INDUCED PULSATING PRESSURE  30
STUDY ON DYNAMIC RESPONSE OF REACTOR CORE BARREL UNDER PUMP-...
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30th International Congress on Sound and Vibration, ICSV 2024
作者: Ye, Xianhui Cai, Fengchun Huang, Xuan Feng, Zhipeng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The flow-induced vibration (FIV) problem is widely present in nuclear power plants and has caused numerous engineering accidents. Therefore, it has been highly valued by the nuclear engineering community for a long ti... 详细信息
来源: 评论
Research on the vibration reduction and sound radiation index properties of the cabin with internal equipment  26
Research on the vibration reduction and sound radiation inde...
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26th International Congress on Sound and Vibration, ICSV 2019
作者: Wenzheng, Zhang Bihao, Wang Xiaozhou, Jiang Bin, Lan Haiyang, Song Fengchun, Cai Xianhui, Ye Jiabin, Feng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Suitable vibration and noise indices which provide technical direction for vibration and noise reduction, play a very important role in structure analysis and validated test. The contribution of foundation impedance i... 详细信息
来源: 评论