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检索条件"机构=Science and Technology on Reactor system Design Technology Laboratory"
1276 条 记 录,以下是131-140 订阅
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A combined reactivity control pattern on a floating nuclear power plant  27
A combined reactivity control pattern on a floating nuclear ...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Zhou, Bingyan Song, Danrong Chen, Zhang Chai, Xiaoming Xiang, Hongzhi Hu, Yuying Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
In this study, a new combined reactivity control pattern is presented to lower the power peaking factor on a floating nuclear power plant. In the pattern the whole cycle length is divided into several boron-adjusting ... 详细信息
来源: 评论
Fatigue crack growth model for edge sliding mode  14
Fatigue crack growth model for edge sliding mode
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14th International Conference on Fracture, ICF 2017
作者: Shi, K.K. Zheng, B. Bai, X.M. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The inherent law between fatigue behaviours of shear-type representative volume element and mode-II fatigue crack growth is found in the range of cycle plastic zone near the crack tip. Prediction models for mode-II fa... 详细信息
来源: 评论
Study on Acoustic-Induced Vibration (AIV) by reactor coolant pump at secondary support structure  48
Study on Acoustic-Induced Vibration (AIV) by reactor coolant...
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48th International Congress and Exhibition on Noise Control Engineering, INTER-NOISE 2019 MADRID
作者: Huang, Xuan Cai, Fengchun Wu, Wanjun Qi, Huanhuan Feng, Zhipeng Liu, Shuai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The reactor coolant pump is the core equipment of nuclear power stations. During the operation of reactor coolant pump, acoustic pulsations are generated due to nonuniform flow within the reactor coolant pump and pass... 详细信息
来源: 评论
Stress intensity factors for penetrate radial cracks in reactor coolant pump flywheel by weight function method  14
Stress intensity factors for penetrate radial cracks in reac...
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14th International Conference on Fracture, ICF 2017
作者: Shi, K.K. Zheng, B. Gao, S.Q. Chen, J.G. Lv, X. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Stress intensity factors for penetrate radial crack at center of keyway and at keyway corner under the plane stress, the plane strain and the three dimensional, based on weight function method, is determined by finite... 详细信息
来源: 评论
Application of optimus in sensitivity analysis of dynamic response of reactor coolant system  27
Application of optimus in sensitivity analysis of dynamic re...
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27th International Congress on Sound and Vibration, ICSV 2021
作者: Yanli, Yuan Xianhui, Ye WenZheng, Zhang Lijuan, Li Zhenyu, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
In this paper, the sensitivity of the dynamic response of reactor coolant system to the input parameters is investigated through OPTIMUS integrated platform, taking the stiffness of the dampers which support the steam... 详细信息
来源: 评论
Development of three-dimensional neutron kinetics code based on high order nodal expansion method in hexagonal-Z geometry  26
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2018 26th International Conference on Nuclear Engineering, ICONE 2018
作者: Chao, Guo Yu, Liu Hangxing, He Luguo, Liu Xiaoyu, Wang Sufang, Xin Peiying, Li Xiaoli, Wu Hongsheng, Yuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
To solve three-dimensional kinetics problems, a high order nodal expansion method for hexagonal-z geometry(HONEM) and a Runge-Kutta (RK) method are respectively adopted to deal with the spatial and temporal problem. I... 详细信息
来源: 评论
Multiple branches coupling property and design of PRHRs
Multiple branches coupling property and design of PRHRs
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2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials
作者: Zhuohua, Zhang Xu, Ran Feng, Li Lin, Xian Ke, Zhou Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Nuclear reactor applied on ship or floating platform recommend miniaturization and optimization of PRHRs. Due to much larger volume and heat transfer area in PRHRs heat exchanger, miniaturization and design of PRHRs n... 详细信息
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The preliminary performance study of ATF with M3 fuel and Zr-4 cladding  24
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2016 24th International Conference on Nuclear Engineering, ICONE 2016
作者: Chunyu, Yin Teng, Tu Tang, Changbing Jiao, Yongjun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China ChengduSichuan China
Metal matrix microencapsulated (M3) fuel is one of the research directions on Accident Tolerant Fuel (ATF). In this article, it provides one of ATF design which consists of BISO (Bistructural ISOtropic) particles embe... 详细信息
来源: 评论
Validation of sop procedure for dealing with FWLB  22
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2014 22nd International Conference on Nuclear Engineering, ICONE 2014
作者: Yaou, Shen Wei, Chen Daishun, Huang Guijun, Leng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The State Oriented Procedure (SOP) is developed to improve the existing emergency operation procedures, namely, the Event Oriented Procedure (EOP). It is developed based on the finite Nuclear Steam Supply system (NSSS... 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