Bub-Dong Chung

Safety evaluation of accident-tolerant FCM fueled core with SiC-coated zircalloy cladding for design-basis-accidents and beyond DBAs

Ji-Han Chun, Sung-Won Lim, Bub-Dong Chung et al. · Nuclear Engineering and Design · 2015 · 46 citations · Full text

Materials Science, Ceramic Matrix Composite, Engineering +5

Two phase natural circulation and the heat transfer in the passive residual heat removal system of an integral type reactor

Young-Jong Chung, Hee‐Cheol Kim, Bub-Dong Chung et al. · Annals of Nuclear Energy · 2005 · 35 citations

Heat Transfer Process, Engineering, Heat Recovery +10

Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark

T. Skorek, A. de Crécy, A. Kovtonyuk et al. · Nuclear Engineering and Design · 2019 · 31 citations · Full text

Thermodynamic Modelling, Engineering, Thermal Hydraulics +12

Thermo-hydraulic characteristics of the helically coiled tube and the condensate heat exchanger for SMART

Young-Jong Chung, Hyung Jun Kim, Bub-Dong Chung et al. · Annals of Nuclear Energy · 2013 · 23 citations

Condensate Heat Exchanger, Engineering, Heat Exchanger +8

Safety evaluation of small-break LOCA with various locations and sizes for SMART adopting fully passive safety system using MARS code

Ji-Han Chun, Bub-Dong Chung, Guy-Hyung Lee et al. · Nuclear Engineering and Design · 2014 · 14 citations

Safety Engineering, Safety-critical System, Reliability Engineering +9