Zobrazeno 1 - 3
of 3
pro vyhledávání: '"Zhongyun Ju"'
Autor:
Wen Ding, Kui Zhang, Dalin Zhang, Ronghua Chen, Zhongyun Ju, Caihong Xu, Ting Wang, Wenxi Tian, Suizheng Qiu
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 3, Pp 115-122 (2023)
The safety injection (SI) system might be put into use, and the coolant at high temperature will mix with the supcooled water under Loss Of Coolant Accident (LOCA). The thermo-hydraulic phenomena associated with the thermal mixing of coolant and supc
Externí odkaz:
https://doaj.org/article/0d995bfce24a4c298e42e5e7d705eaa4
Autor:
Martin, Kevin, Casamor, Max, Martinez-Quiroga, Victor, Perez-Ferragut, Marina, Zhongyun, Ju, Freixa, Jordi
Publikováno v:
In Nuclear Engineering and Design October 2024 427
Publikováno v:
Research Journal of Applied Sciences, Engineering and Technology. 5:4123-4128
In this study, we obtain the flow signals before and after the ONB through natural circulation experiments under pressure conditions of 0.15MPa and 0.3MPa. Researches were conducted by applying nonlinear analysis techniques. Results revealed that the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fffcdcd03aebc1c93f8152a66e22575a
https://doi.org/10.19026/rjaset.5.4636
https://doi.org/10.19026/rjaset.5.4636