研究论文
Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer
Seong Dae Park, Seok Bin Seo, Yeongshin Jeong, Dong-Wook Jerng, In Cheol Bang
Korea Atomic Energy Research Institute Ulsan National Institute of Science and Technology Chung-Ang University
来源Annals of Nuclear Energy
年份2017
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学科主题
工程Nuclear reactor physics and engineering
Nuclear Engineering Thermal-Hydraulics · Heat transfer and supercritical fluids
参考文献 12
Laminar, Transition, and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles
被引 91Felix Engel, R.A. Markley, A.A. Bishop · Nuclear Science and Engineering · 1979
TURBULENT FLOW IN PIPES, WITH PARTICULAR REFERENCE TO THE TRANSITION REGION BETWEEN THE SMOOTH AND ROUGH PIPE LAWS.
被引 1,951C F Colebrook · Journal of the Institution of Civil Engineers · 1939
Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters
被引 428Shih-Kuei Cheng, N.E. Todreas · Nuclear Engineering and Design · 1986
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引用本文 13
Thermal-hydraulic analysis of a 7-pin sodium-cooled fast reactor wire-wrapped fuel bundle
被引 26Dianle Wang, Changhong Peng, Yun Guo · International Journal of Heat and Mass Transfer · 2020
Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assembly
被引 26Yeongshin Jeong, Ji Yong Kim, In Cheol Bang · Annals of Nuclear Energy · 2019
Numerical analysis of the three-dimensional flow phenomena in a 19-pin wire-wrapped tight lattice bundle
被引 21Junlong Li, Yao Xiao, Guanqun Ding · International Journal of Heat and Mass Transfer · 2022
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