Zobrazeno 1 - 10
of 32
pro vyhledávání: '"Minfu Zhao"'
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
Critical heat flux (CHF) is one of the most concerned thermal hydraulic phenomena in reactor safety analysis. It involves complex two-phase flow heat transfer mechanism, and has not been fully understood, so the prediction of critical heat flux mainl
Externí odkaz:
https://doaj.org/article/d68e2acbcaab42cb8a75bfad3efc40a6
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
The printed circuit heat exchanger (PCHE) is the key equipment of the supercritical carbon dioxide Brayton cycle applied to sodium cooled fast reactor. It is required that the equipment not only can operate in high temperature and high pressure envir
Externí odkaz:
https://doaj.org/article/be7d5f2266c849dd9e3ee3f05bdb4ffb
Autor:
Haoran Ju, Mingjun Wang, Yingjie Wang, Minfu Zhao, Wenxi Tian, Tiancai Liu, G.H. Su, Suizheng Qiu
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 9, Pp 1945-1954 (2020)
Subchannel code is one of the effective simulation tools for thermal-hydraulic analysis in nuclear reactor core. In order to reduce the computational cost and improve the calculation efficiency, empirical correlation of turbulent mixing coefficient i
Externí odkaz:
https://doaj.org/article/60789a348da444c790dd25bca8c52678
Autor:
Yingjie Wang, Mingjun Wang, Haoran Ju, Minfu Zhao, Dalin Zhang, Wenxi Tian, Tiancai Liu, Suizheng Qiu, G.H. Su
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 7, Pp 1386-1395 (2020)
High fidelity nuclear reactor fuel assembly simulation using CFD method is an effective way for the structure design and optimization. The validated models and user practice guidelines play critical roles in achieving reliable results in CFD simulati
Externí odkaz:
https://doaj.org/article/2cb947089b6d4026bd8b1581e132a5c3
Publikováno v:
Frontiers in Earth Science, Vol 8 (2020)
The investigation of critical flow model for supercritical pressure condition is relatively rare. Based on isentropic flow and thermal equilibrium assumptions, a model is derived to calculate discharge flow rate and critical pressure. Considering the
Externí odkaz:
https://doaj.org/article/3ac7d3dd3e4644f3ad96ab974b60667a
Publikováno v:
The Journal of Physical Chemistry A. 126:3543-3548
Publikováno v:
Volume 7A: Thermal-Hydraulics and Safety Analysis.
Two-phase flow instability plays an very important role in operation safety and reliability of heat exchange equipment. The mechanism of two-phase flow instability was very complicated. Two-phase flow instability may occur when the fluid volume in th
Autor:
Wang Yingjie, Tiancai Liu, Haoran Ju, Guanghui Su, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Dalin Zhang, Minfu Zhao
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 7, Pp 1386-1395 (2020)
High fidelity nuclear reactor fuel assembly simulation using CFD method is an effective way for the structure design and optimization. The validated models and user practice guidelines play critical roles in achieving reliable results in CFD simulati
Publikováno v:
SCIENTIA SINICA Technologica. 51:324-340
Publikováno v:
Chemical Physics. 562:111650