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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是111-120 订阅
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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
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
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
The instrumentation and control system for small modular reactor ACP100  9
The instrumentation and control system for small modular rea...
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9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015
作者: Chen, Zhi Song, Dan-Rong Liao, Long-Tao You, Kai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
The small modular reactor (SMR), which is coded ACP100 and developed by China National Nuclear Corporation(CNNC), is an innovative PWR based on existing PWR technology, adapting "passive" safety system and &... 详细信息
来源: 评论
Large eddy simulation of turbulent flow in rod bundle with spacer grids
Large eddy simulation of turbulent flow in rod bundle with s...
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Zonglan, Wei Xiao, Chu Yu, Zhang Songtao, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
来源: 评论
Research on periodic test scheme of safety digital control system for nuclear power plant  27
Research on periodic test scheme of safety digital control s...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Xie, Weibo Wu, Zhiqiang Zeng, Shan Li, Yutong Hu, Qingren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The main trend in the development of the local power plant control system is to adopt digital safety DCS system with rather strong ability of self-diagnosis. Apart from the self-diagnosis, it is also necessary to carr... 详细信息
来源: 评论
Improved core design of the supercritical water-cooled reactor CSR1000
Improved core design of the supercritical water-cooled react...
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Wang, Lianjie Lu, Di Yang, Ping Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
来源: 评论
Numerical simulation of sealing behavior of C-ring for reactor Pressure Vessel  23
Numerical simulation of sealing behavior of C-ring for React...
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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Dong, Yuanyuan Luo, Ying Zhang, Liping Nuclear Power Institute of China Science and Technology Reactor System Design Technology Laboratory Chengdu Sichuan China
C-ring, whose sealing behavior is the key to the sealing structure, is one of the main seal-rings for reactor Pressure Vessel. A finite element model with less simplification has been established using ANSYS APDL to s... 详细信息
来源: 评论
Calculation of higher eigenpairs of the transport equation Using IRAM based on domain decomposition
Calculation of higher eigenpairs of the transport equation U...
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Wu, Wenbin Yu, Yingrui Li, Qing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
来源: 评论
Research on Ultra High Flux Research reactor  23rd
Research on Ultra High Flux Research Reactor
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Zhang, Xue Yu, Hongxing Xia, Bangyang Li, Wenjie Zhang, Xilin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The lack of fast neutron irradiation test equipment is a key practical factor that restricts the development of the new generation nuclear energy technology with fast reactor as the core in China. Scarce isotopes such... 详细信息
来源: 评论