Stebėti
Dong Gu Kang
Dong Gu Kang
Korea Institute of Nuclear Safety
Patvirtintas el. paštas kins.re.kr
Pavadinimas
Cituota
Cituota
Metai
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
492013
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
412011
CFD analysis of thermally stratified flow and conjugate heat transfer in a PWR pressurizer surgeline
JC Jo, DG Kang
342010
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
312014
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
272019
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
242016
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
222020
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
142008
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
122019
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, ...
122012
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
102020
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
102018
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
92021
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
92007
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
82017
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
72021
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
62020
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
52013
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
42009
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
42008
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Straipsniai 1–20