Analysis of critical pipe break sizes leading to reactor pressure vessel liquid level collapse and core uncovery with APROS

Thermo-fluid Dynamics of Two-phase Flow

賞雅 寛而 · Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan · 2006 · 288 citations · Full text

Engineering, Mechanical Engineering, Physics +11

Thermal hydraulic phenomena related to small break LOCAs in AP1000

W.W. Wang, G.H. Su, Suizheng Qiu et al. · Progress in Nuclear Energy · 2011 · 74 citations

Engineering, Mechanical Engineering, Heat Transfer +7

Simulation and analysis on 10-in. cold leg small break LOCA for AP1000

Jiangcun Yang, W.W. Wang, Suizheng Qiu et al. · Annals of Nuclear Energy · 2012 · 49 citations

Engineering, Mechanical Engineering, Applied Mechanics +1

Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method

Ronghua Chen, Maolin Tian, Sen Chen et al. · Annals of Nuclear Energy · 2017 · 38 citations

Engineering, Computational Engineering, Nuclear Engineering +16

Research on thermal hydraulic behavior of small-break LOCAs in AP1000

W.W. Wang, G.H. Su, Wenxi Tian et al. · Nuclear Engineering and Design · 2013 · 24 citations

Engineering, Mechanical Engineering, Heat Transfer +9