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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是281-290 订阅
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A simplified two-node coarse-mesh finite difference method for pin-wise calculation with SP3
A simplified two-node coarse-mesh finite difference method f...
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2020 International Conference on Physics of reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
作者: Zhao, Wenbo Yu, Yingrui Chai, Xiaoming Ning, Zhonghao Zhang, Bin Cai, Yun Liu, Kun Peng, Xingjie Yu, Junchong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
For accurate and efficient pin-by-pin core calculation of SP3 equations, a simplified two-node Coarse Mesh Finite Difference (CMFD) method with the nonlinear iterative strategy is proposed. In this study, the two-node... 详细信息
来源: 评论
Theoretical exploration of heat transfer characteristics of liquid metals
Theoretical exploration of heat transfer characteristics of ...
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2020 Transactions of the American Nuclear Society, ANS 2020
作者: Shen, Yaou Peng, Shinian Yan, Mingyu Zhang, Yu Deng, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
来源: 评论
Research on thermal diffusion coefficient calculation for subchannels with spacer grid using CFD methodology  14
Research on thermal diffusion coefficient calculation for su...
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14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019
作者: Chen, Xi Du, Sijia Liu, Yu Qian, Libo Liu, Lili Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Thermal Diffusion Coefficient (TDC) is one of the most important parameters in subchannel analysis codes. Abundant research results demonstrate that TDC is mainly determined by the structures of fuel assembly, especia... 详细信息
来源: 评论
Capillary Evaporating Film Model for a Screen-Wick Heat Pipe
SSRN
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SSRN 2022年
作者: Ma, Yugao Zhang, Yingnan Yu, Hongxing Huang, Shanfang Deng, Jian Chai, Xiaoming Zeng, Chang Zhang, Zhuohua He, Xiaoqiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Engineering Physics Tsinghua University Beijing100084 China
Screen-wick heat pipes are efficient passive heat transfer devices. The heat transfer capacity is determined by the capillary pressure, which is related to the film curvature inside the screen wick. A capillary evapor... 详细信息
来源: 评论
Perceived vs. Objective Human Performance in Diagnostic Tasks: Under-Confidence or Over-Confidence?
SSRN
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SSRN 2022年
作者: Lyu, Xi Li, Zhizhong Ma, Quan She, Manrong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Industrial Engineering Tsinghua University Beijing100084 China
Humans are not very good at assessing their own performance, and usually exhibit over-confidence. Little effort has been done to investigate how and how well diagnosticians perceive their performance of sub-processes ... 详细信息
来源: 评论
Study on flow modes of open natural circulation with low height difference under low power conditions
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International Journal of Advanced Nuclear reactor design and technology 2020年 2卷 10-14页
作者: Yi, Li Jianchuang, Sun Hang, Peng Cheng, Xiang Quan, Biao Cao, Xiaxin Jian, Zhou Ming, Ding 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 Harbin150001 China
Open natural circulation systems are widely applied in the field of energy and chemical industries. Under some special conditions, open natural circulation systems with low height difference need to be applied, but re... 详细信息
来源: 评论
Applying multi-scale simulations to materials research of nuclear fuels:A review
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Materials Reports(Energy) 2021年 第3期1卷 64-80页
作者: Chunyang Wen Di Yun Xinfu He Yong Xin Wenjie Li Zhipeng Sun School of Nuclear Science and Technology Xi'an Jiaotong UniversityXi'an710049China State Key Laboratory of Multiphase Flow Xi'an Jiaotong UniversityXi'an710049China China Institute of Atomic Energy Beijing102413China Key Laboratory of Nuclear Reactor System Design Technology Nuclear Power Institute of ChinaChengdu610213China
Computational simulation is an important technical means in research of nuclear fuel *** nuclear fuel issues are inherently multi-scopic,it is imperative to study them with multi-scale simulation *** present,the devel... 详细信息
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Safety assessment of UN/Zr fuel with SiC cladding under large break loss-of-coolant accident  14
Safety assessment of UN/Zr fuel with SiC cladding under larg...
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14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019
作者: Qian, Libo Yu, Hongxing Sun, Yufa Deng, Jian Wu, Dan Ding, Shuhua Chen, Wei Li, Zhongchun Chen, Xi Liu, Lili Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan610213 China
Accident Tolerant Fuel (ATF), which is aiming at upgrading safety characteristics of nuclear fuel and cladding under design basis and design extension conditions, has drawn more and more attention since Fukushima acci... 详细信息
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Simulation analysis on the pressurizer degassing sub-system of module small reactor (ACP100)
Simulation analysis on the pressurizer degassing sub-system ...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Zhiyun, Cai Yun, Ren Jianyong, Lai Yulong, Zhang Hang, Liu Xianghong, Liu Minghao, Liu Zhu, Ye Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610041 China
A pressurizer degassing sub-system is designed in Module Small reactor(ACP100), which can be used to vent the noncondensable gas dissolved in reactor Coolant during plant shutdown period by opening the remote degassin... 详细信息
来源: 评论
Optimization design for the configuration parameters of helical-coil steam generator volume
Optimization design for the configuration parameters of heli...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Fang, Hongyu Wang, Li Zhu, Dahuan Cai, Rong Jiang, Xiaowei Zhang, Dan Qian, Libo Wu, Dan Science and Technology on Reactor System Design Technology Laboratory Chengdu China Sun YAT-SEN University Guangzhou China
With the development of the nuclear energy industry, small modular reactors (SMRs) have become an important option in China's energy development due to their advantages in terms of safety and economics. The helica... 详细信息
来源: 评论