Zobrazeno 1 - 10
of 78
pro vyhledávání: '"ZHAO Yafeng"'
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 8, Pp 1504-1513 (2023)
Lead-based reactor coolant has high thermal conductivity, good thermal expansion and strong natural circulation ability, which has outstanding advantages in safety, economy and miniaturization. At the same time, lead-bismuth reactors have potential a
Externí odkaz:
https://doaj.org/article/2e269a4a7e1c4ed5bb3288bc8389f0e0
Publikováno v:
Guan'gai paishui xuebao, Vol 40, Iss 12, Pp 142-148 (2021)
【Background and objective】 Critical water depth is an important design parameter of open channels. Since standard horseshoe-shaped open channel does not have strict requirements on geological environment and is convenient to construct, it has bee
Externí odkaz:
https://doaj.org/article/7513ddbea77048f794e85d80ab74e33c
Autor:
Yu, Qifan, Zhao, Yafeng, Chen, Yutong, Liu, Zhipeng, Wang, Chenglong, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, SU, G.H.
Publikováno v:
In Annals of Nuclear Energy January 2024 195
Autor:
Yu, Qifan, Fang, Yuliang, Zhao, Yafeng, Qiu, Suizheng, Wang, Chenglong, Zhang, Dalin, Tian, Wenxi, SU, G.H.
Publikováno v:
In International Journal of Heat and Mass Transfer 15 June 2023 207
Autor:
Zhao, Yafeng1 (AUTHOR) 2022112490@nefu.edu.cn, Jiang, Chenglong1 (AUTHOR), Wang, Dongdong1 (AUTHOR), Liu, Xiaolu1 (AUTHOR), Song, Wenhua1 (AUTHOR), Hu, Junfeng1 (AUTHOR) hujunfeng@nefu.edu.cn
Publikováno v:
Agronomy. Dec2023, Vol. 13 Issue 12, p2863. 15p.
Publikováno v:
In Annals of Nuclear Energy February 2023 181
Publikováno v:
In International Journal of Heat and Mass Transfer January 2023 200
Autor:
Zhang, Jishi, Lu, Jingrong, Huang, Haidong, Liu, Xiaoning, Zhao, Yafeng, Wang, Zhiyang, Mo, Jinlei
Since the 1920s, when the three oscillations ENSO, NAO and NPO were found and defined, the theory of ocean-atmosphere coupling is particularly important in explaining the phenomena of atmospheric physics, then defined more than ten climate indexes, s
Externí odkaz:
http://arxiv.org/abs/1709.07146
Thermal-hydraulic Simulation and Steam Cavity Diffusion of SGTR Accident in Lead-cooled Fast Reactor
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 11, Pp 2015-2023 (2022)
Lead-cooled fast reactor (LFR) is known as a typical reliable new type reactor by the US Department of Energy (DOE), and the potential accidents of LFR are necessary to assess. Steam generator tube rupture (SGTR) accident can cause high-pressure hype
Externí odkaz:
https://doaj.org/article/d5f8152b28144bbca7488e203433f306
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