Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Yunke Zhong"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2016 (2016)
In order to investigate single bubble evolution, a boiling phase change model in subcooled flow boiling is proposed in this paper, and VOF model combined with phase change model is adopted to simulate the single bubble growth and movement. The effect
Externí odkaz:
https://doaj.org/article/afa1e39b55cf41b0a8a21bf5ac5d90cb
Autor:
Jiancheng Tang, Youkun Fu, Yunke Zhong, Lei Yuan, Cai Lijun, Sijia Li, Qiang Li, Jinlong Chen, Xin Chen
Publikováno v:
IEEE Transactions on Applied Superconductivity. 31:1-4
HL-2M, a new generation of tokamak, has been built continuously in 2020 in Southwestern Institute of Physics, China National Nuclear Corporation, and the first plasma discharge was successfully achieved in 12th, Dec. This tokamak experiment device ha
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0bc7440d6b50793e4ccafdf304b15d8c
https://doi.org/10.1109/tasc.2021.3110465
https://doi.org/10.1109/tasc.2021.3110465
CFD simulation on the flow and heat transfer characteristics of mist flow in wire-wrapped rod bundle
Publikováno v:
Nuclear Engineering and Design. 345:62-73
The heat transfer characteristics of post-CHF (critical heat flux) is very important and complicated, which has aroused wide attention in the topic of nuclear reactor safety. In this paper, a phase change model of liquid droplet during mist flow is p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4ac88cea55917bf19615ef6b0f6dffe3
https://doi.org/10.1016/j.nucengdes.2019.02.003
https://doi.org/10.1016/j.nucengdes.2019.02.003
Publikováno v:
Heat Transfer Research. 49:1199-1218
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::50e58602b0fdbcf88219f1c19d30e488
https://doi.org/10.1615/heattransres.2018016441
https://doi.org/10.1615/heattransres.2018016441
Autor:
Youkun Fu, Jinlong Chen, Enpeng Yang, Lei Yuan, Jiancheng Tang, Xin Chen, Qiang Li, Sijia Li, Genliang Zhu, Cai Lijun, Yunke Zhong
Publikováno v:
Fusion Engineering and Design. 172:112761
The 500 W@4.5 K helium refrigeration system operated in HL-2M Tokamak is the first domestically made cryogenic system independently designed and manufactured in China. It is expected to cool down HL-2M cryousers for the first time around June 2021. I
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::85d76143198edbef0df0037ac6022944
https://doi.org/10.1016/j.fusengdes.2021.112761
https://doi.org/10.1016/j.fusengdes.2021.112761
Publikováno v:
Nuclear Engineering and Design. 304:70-79
The effectiveness of in-vessel retention (IVR) by external reactor vessel cooling (ERVC) strongly depends on the critical heat flux (CHF). As long as the local CHF does not exceed the local heat flux, the lower head of the pressure vessel can be cool
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c0b40fe9d254a986d26f5bb2c0f0801f
https://doi.org/10.1016/j.nucengdes.2016.04.043
https://doi.org/10.1016/j.nucengdes.2016.04.043
Numerical investigation on the characteristics of two-phase flow in fuel assemblies with spacer grid
Publikováno v:
Kerntechnik. 81:276-285
In pressurized water reactors (PWRs), the spacer grids of the fuel assembly has significant impact on the thermal-hydraulic performance of the fuel assembly. Particularly, the spacer grids with the mixing vanes can dramatically enhance the secondary
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::684b74bf539f5799bfc148afb63487ac
https://doi.org/10.3139/124.110747
https://doi.org/10.3139/124.110747
Publikováno v:
Applied Thermal Engineering. 103:1416-1426
The turbulent flow behavior and heat transfer performance of the rod bundle with spacer grid have significant effect on the thermal–hydraulic characteristics in Pressurized Water Reactor (PWR). The complex structure of the spacer grid includes dimp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::48bba287bf7e7dc4c94b2959347d692f
https://doi.org/10.1016/j.applthermaleng.2016.05.028
https://doi.org/10.1016/j.applthermaleng.2016.05.028
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2016 (2016)
In order to investigate single bubble evolution, a boiling phase change model in subcooled flow boiling is proposed in this paper, and VOF model combined with phase change model is adopted to simulate the single bubble growth and movement. The effect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5c6a1921ed92c00cce6e5c2f052b534e
https://doaj.org/article/afa1e39b55cf41b0a8a21bf5ac5d90cb
https://doaj.org/article/afa1e39b55cf41b0a8a21bf5ac5d90cb