A combined deterministic and probabilistic procedure for safety assessment of beyond design basis accidents in nuclear power plant: application to ECCS performance assessment … DG Kang, SH Ahn, SH Chang Nuclear Engineering and Design 260, 165-174, 2013 | 49 | 2013 |
Fluid–structure interaction analysis for pressurizer surge line subjected to thermal stratification DG Kang, MJ Jhung, SH Chang Nuclear Engineering and Design 241 (1), 257-269, 2011 | 41 | 2011 |
CFD analysis of thermally stratified flow and conjugate heat transfer in a PWR pressurizer surgeline JC Jo, DG Kang | 34 | 2010 |
The safety assessment of OPR-1000 nuclear power plant for station blackout accident applying the combined deterministic and probabilistic procedure DG Kang, SH Chang Nuclear Engineering and Design 275, 142-153, 2014 | 31 | 2014 |
Detached eddy simulation of turbulent and thermal mixing in a T-junction DG Kang, H Na, CY Lee Annals of nuclear energy 124, 245-256, 2019 | 27 | 2019 |
Analysis of LBLOCA using best estimate plus uncertainties for three-loop nuclear power plant power uprate DG Kang Annals of Nuclear Energy 90, 318-330, 2016 | 24 | 2016 |
Comparison of statistical methods and deterministic sensitivity studies for investigation on the influence of uncertainty parameters: Application to LBLOCA DG Kang Reliability Engineering & System Safety 203, 107082, 2020 | 22 | 2020 |
CFD application to the regulatory assessment of FAC-caused CANDU feeder pipe wall thinning issue DG Kang, JC Jo Nuclear Engineering and Technology 40 (1), 37, 2008 | 14 | 2008 |
Evaporation of sessile water droplet on heated surface with needle-shaped nanostructures by pre-boiling oxidation process DG Kang, GM Nam, WK In, CY Lee Experimental Thermal and Fluid Science 101, 193-200, 2019 | 12 | 2019 |
Comparison report of open calculations for ATLAS Domestic Standard Problem (DSP 02) KY Choi, YS Kim, KH Kang, S Cho, HS Park, NH Choi, BD Kim, KH Min, ... | 12 | 2012 |
One-dimensional ex-vessel coolability analysis of debris beds formed in OPR1000 pre-flooded reactor cavity H Na, DG Kang, YH Ryu, HJ Lee Annals of Nuclear Energy 138, 107123, 2020 | 10 | 2020 |
Minimum film boiling temperature and minimum heat flux in pool boiling of high-temperature cylinder quenched by aqueous surfactant solution DG Kang, JH Kim, CY Lee Journal of Mechanical Science and Technology 32, 5919–5926, 2018 | 10 | 2018 |
A preliminary study on concrete ablation during ex-vessel cooling in pre-flooded Westinghouse 3-loop NPP reactor cavity H Na, DG Kang, S Pak, HJ Lee Annals of Nuclear Energy 151, 107838, 2021 | 9 | 2021 |
Buoyant convection in an enclosure under time-periodic magnetizing force DG Kang, JM Hyun International journal of heat and mass transfer 50 (3-4), 605-615, 2007 | 9 | 2007 |
The effect of nodalization and temperature of reactor upper region: Sensitivity analysis for APR-1400 LBLOCA DG Kang Annals of Nuclear Energy 99, 28-35, 2017 | 8 | 2017 |
Uncertainty quantification analysis and statistical estimation for LBLOCA in a PWR using Monte-Carlo and alternative methods DG Kang Annals of Nuclear Energy 150, 107868, 2021 | 7 | 2021 |
Experimental study on pool boiling regime transitions of vertical rod quenched in aqueous surfactant solutions using inverse heat transfer analysis DG Kang, JH Kim, S Kim, BJ Zhang, CY Lee Journal of Mechanical Science and Technology 34, 4753-4761, 2020 | 6 | 2020 |
Evaluation for Effect of Upper Head Nodalization and Temperature in OPR1000 Plant BG Huh, DG Kang, SH Yoo, KW Seul 22nd International Conference Nuclear Energy for New Europe, Slovenia, 2013 | 5 | 2013 |
Numerical calculation of shear stress distribution on the inner wall surface of CANDU reactor feeder pipe conveying two-phase coolant JC Jo, DG Kang, KW Roh | 4 | 2009 |
CFD analysis of thermally stratified flow and heat transfer in a PWR pressurizer surge line DG Kang, JC Jo ASME Pressure Vessels and Piping Conference 48272, 29-39, 2008 | 4 | 2008 |