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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是351-360 订阅
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Multiple choices of reactor core nuclear design for ACP100's application in different scenarios
Multiple choices of reactor core nuclear design for ACP100's...
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2020 International Conference on Physics of reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
作者: Wang, Liangzi Ju, Haitao Li, Qing Qin, Dong Wang, Lianjie Yu, Yingrui Ning, Zhonghao Wang, Chenlin Guo, Rui Wang, Shuai Zhang, Bin Xiang, Hongzhi Lou, Lei Sun, Wei Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China NO. 328 Section 1 Changshun Ave Shuangliu District Sichuan Chengdu China
ACP100 NPP designed by CNNC (China National Nuclear Corporation) is a 125MWe, multi-purpose small modular reactor based on pressurized water reactor technology;it adopts the integrated reactor technology. Different ap... 详细信息
来源: 评论
RMC/ANSYS Multi-physics coupling solutions for heat pipe cooled reactors analyses
RMC/ANSYS Multi-physics coupling solutions for heat pipe coo...
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2020 International Conference on Physics of reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
作者: Ma, Yugao Liu, Minyun Chen, Erhui Xie, Biheng Chai, Xiaoming Huang, Shanfang Wang, Kan Yu, Hongxing Department of Engineering Physics Tsinghua University Beijing100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the co... 详细信息
来源: 评论
Experimental study on multi-channel jets in plate assembly under blockage condition
Experimental study on multi-channel jets in plate assembly u...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Huijian, Huang Peng, Wang Dongyang, Li Tan, Sichao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Harbin Heilongjiang China
In the nuclear field, the reactor using plate fuel assembly forms multiple jets at exit. So, it's meaningful to study multiple jets to learn the behavior of the coolant when it leaves the core. This paper uses PIV... 详细信息
来源: 评论
Study on natural circulation flow instabilities in rod bundle channel under rolling condition
Study on natural circulation flow instabilities in rod bundl...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Cheng, Kun Deng, Jian Cai, Rong Qian, Libo Qi, Peiyao Ke, Bingzheng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Heilongjiang150001 China
The effects of rolling condition on the flow instability characteristics of natural circulation (NC) in rod bundle channel were experimentally studied. A 3×3 rod bundle channel is used as the testing section. The... 详细信息
来源: 评论
Revealing the Correlation between Microstructure and Fatigue Crack Growth Behaviors in Ti-6al-3nb-2zr-1mo Alloy
SSRN
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SSRN 2022年
作者: Yang, Pengfei Sun, Qi Zheng, Xuechao Mi, Xue Chai, Linjiang Zhu, Minhao Tribology Research Institute School of Mechanical Engineering Southwest Jiaotong University Chengdu China School of Material Science and Engineering Southwest Jiaotong University Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China School of Materials Science and Engineering Chongqing University of Technology Chongqing China
In the current work, the correlation between microstructural features and fatigue crack growth (FCG) behaviors in Ti-6Al-3Nb-2Zr-1Mo alloy is investigated by a combination of electron backscatter diffraction (EBSD), e... 详细信息
来源: 评论
Sound propagation characteristic of phononic crystals pipeline with periodic vibration isolation mass
Sound propagation characteristic of phononic crystals pipeli...
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2020 Transactions of the American Nuclear Society, ANS 2020
作者: Zeng, Qingna Wang, Donghui Zang, Fenggang Zhang, Yixiong Jiang, Xiaozhou Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 328# 1st section Changshun Dadao Avenue Chengdu610213 China
来源: 评论
Research for the heat leakage caused by gaps on barrel insulation structure of reactor pressure vessel
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International Journal of Advanced Nuclear reactor design and technology 2019年 1卷 30-42页
作者: Tian, Qiu Ying, Luo Yang, Qiu Yu-guang, Li Guo-fu, Xie Li-cai, Yang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China ChengduSichuan Province610213 China
Due to the function requirements of the Cavity Injection and Cooling system, the barrel insulation structure of HPR1000 reactor pressure vessel has been greatly improved compared with the previous projects. In the pas... 详细信息
来源: 评论
Capillary Limit of a Sodium Screen-Wick Heat Pipe
SSRN
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SSRN 2022年
作者: Ma, Yugao Wang, Xueqing Yu, Hongxing Huang, Shanfang Zhang, Yingnan Huang, Jian Su, Guanghui Deng, Jian Chai, Xiaoming Hu, Wenzhen School of Nuclear Science and Technology Xi’an Jiaotong University Shanxi Xi’an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Engineering Physics Tsinghua University Beijing100084 China State Key Laboratory of Multiphase Flow in Power Engineering China
High-temperature alkali-metal heat pipes are passive heat transfer devices, where the capillary pressure created by the menisci in the wick pumps the condensed fluid back to the evaporator. Thus, the heat pipe heat tr... 详细信息
来源: 评论
Experimental Study on the Characteristics of Annular Fluid Film in a Locally Deformed Narrow Rectangular Channel
SSRN
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SSRN 2024年
作者: Wang, Fenze Ren, Quanyao Liu, Haidong Xiao, Yi Chen, Deqi Key Laboratory of Low-grade Energy Utilization Technologies and Systems Chongqing University Ministry of Education Chongqing400044 China Department of Nuclear Engineering and Technology School of Energy and Power Engineering Chongqing University Chongqing400044 China Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China Liangjiang International College Chongqing University of Technology Chongqing401135 China Chongqing Research Institute of HIT Chongqing401151 China School of Flight Technology Civil Aviation Flight University of China Sichuan618307 China China
The study of the characteristics of the annular flow film in the narrow rectangular channel under the localized deformation can provide a research basis for the heat and mass transfer and the hydrodynamic characterist... 详细信息
来源: 评论
Addition of Niobium in Fe-13cr-4.5al-2mo Alloy Used as Atf Cladding: Effect on High Temperature Water Corrosion and In-Situ Electrochemistry
SSRN
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SSRN 2022年
作者: Liao, Jingjing Wang, Hui Wu, Jun Zhang, Wei Xu, Fei Sun, Hongying An, Xuguang Qiu, Shaoyu Chengdu University China Science and Technology on Reactor Fuel and Materials Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China School of Mechanical Engineering Anyang Institute of Technology Henan Anyang455002 China Interdisciplinary Materials Research Center Institute for Advanced Study Chengdu University Sichuan Chengdu610106 China
Niobium addition in candidate accident tolerant fuel (ATF) cladding FeCrAl alloy has received much attention, but its effect on high temperature water corrosion behavior has not been revealed. Four alloys with differe... 详细信息
来源: 评论