您当前的位置:
首页 >
文章列表页 >
Numerical study of thermal-hydraulic characteristics in pipe of floating nuclear reactor under pulsating flow
Thermal Power Generation   Vol. 53, Issue 2, Pages: 93-100(2024)
更新时间:2025-09-28
    • Numerical study of thermal-hydraulic characteristics in pipe of floating nuclear reactor under pulsating flow

    • DOI:10.19666/j.rlfd.202306114    

      CLC: TL333
    • Published:2024

    移动端阅览

  • YAO Yao, LI Chao, QI Peiyao, et al. Numerical study of thermal-hydraulic characteristics in pipe of floating nuclear reactor under pulsating flow[J]. Thermal Power Generation, 2024, 53(2): 93-100. DOI: 10.19666/j.rlfd.202306114.

  •  
  •  
icon
试读结束,您可以激活您的VIP账号继续阅读。
去激活 >
icon
试读结束,您可以通过登录账户,到个人中心,购买VIP会员阅读全文。
已是VIP会员?
去登录 >

0

Views

37

下载量

0

CSCD

Alert me when the article has been cited
提交
Outline
No Sections

Related Articles

Development and numerical simulation for a high efficiency steam soot blower
Influence of inlet airflow maldistribution on performance of double-sided centrifugal induced draft fans
Simulation of temperature field of a 58 MW swirling pulverized coal-fired boiler
Heat-mass transfer and chemical reaction characteristics during carbon dioxide absorption by amine solution in spray scrubber
APPLICATION OF DIFFERENT TURBULENT MODELS IN CALCULATION OF FLOW RESISTANCE IN PIPELINES AND COMPARISON THEREOF

Related Author

LU Quan
LI Yanbing
HAO Jian
HU Jiantao
LU Bingxin
LI Haoran
DONG Kangtian
SHI Qingxin

Related Institution

College of Environmental Science and Engineering, North China Electric Power University
Guohua Sanhe Power Generation Co., Ltd
College of Energy, Power and Mechanical Engineering, North China Electric Power University
School of Mechanical Power Engineering, Harbin University of Science and Technology
China Special Equipment Testing and Research Institute
0