A subchannel and CFD analysis of void distribution for the BWR fuel bundle test benchmark von In, Wang-Kee, Hwang, Dae-Hyun, Jeong, Jae Jun

Volltext

Effect of change in surface condition induced by oxidation on transient pool boiling heat transfer of vertical stainless steel and copper rodlets von Lee, Chi Young, Chun, Tae Hyun, In, Wang Kee

Volltext

Quenching experiment on Cr-alloy-coated cladding for accident-tolerant fuel in water pool under low and high subcooling conditions von Lee, Kwan-Geun, In, Wang-Kee, Kim, Hyun-Gil

Volltext

Quenching Experiments with CrAl-coated Zircaloy Cladding in Reflooding Water Flows von In, Wang Kee, Lee, Kwan Geun

Volltext

Transient pool boiling heat transfer during rapid cooling under saturated water condition von Lee, Chi Young, Kee In, Wang, Koo, Yang Hyun

Volltext

Critical heat flux of oxidized zircaloy surface in saturated water pool boiling von Lee, Chi Young, Chun, Tae Hyun, Kee In, Wang

Volltext

Thermal hydraulic performance assessment of dual-cooled annular nuclear fuel for OPR-1000 von Shin, Chang-Hwan, Chun, Tae-Hyun, Oh, Dong-Seok, In, Wang-Kee

Volltext

Effect of gap width on turbulent mixing of parallel flow in a square channel with a cylindrical rod von Lee, Chi Young, Shin, Chang Hwan, In, Wang Kee

Volltext

Pressure drop in dual-cooled annular and cylindrical solid fuel assemblies for pressurized water reactor von Lee, Chi Young, Shin, Chang Hwan, In, Wang Kee

Volltext

Turbulent vortex trains in narrow square arrayed rod bundles of a dual-cooled nuclear reactor von Kim, Taehwan, Kim, Kyung Min, Bae, Ji-Yeul, Shin, Chang Hwan, In, Wang-Kee, Cho, Hyung Hee

Volltext

Pressure loss coefficient and flow rate of side hole in a lower end plug for dual-cooled annular nuclear fuel von Shin, Chang-Hwan, Park, Ju-Yong, In, Wang-Kee

Volltext

Parametric Analysis of the Axial Nodal Size in a Faster-Running DNBR Program von IN, Wang-Kee, SHIN, Chang-Hwan, CHUN, Tae-Hyun

Volltext

Quenching experiments of vertical Inconel and Zircaloy tubes in internal water flow von Hwang, Gyeong Seop, In, Wang Kee, Lee, Chi Young

Volltext

Evaluation of loss coefficient for an end plug with side holes in dual-cooled annular nuclear fuel von Shin, ChangHwan, Chun, Tae-Hyun, Oh, Dong-Seok, In, Wang-Kee

Volltext

Parametric Analysis of the Axial Nodal Size in a Faster-Running DNBR Program von IN, Wang-Kee, SHIN, Chang-Hwan, CHUN, Tae-Hyun

Volltext

Physical characteristics of a PWR core loaded with micro-cell UO2 pellet fuels von Hwang, Dae Hee, Hong, Ser Gi, In, Wang Kee

Volltext

Evaporation of sessile water droplet on heated surface with needle-shaped nanostructures by pre-boiling oxidation process von Kang, Dong Gu, Nam, Gang Min, In, Wang Kee, Lee, Chi Young

Volltext

Convective heat transfer experiment of rod bundle flow with twist-vane spacer grid von In, Wang Kee, Shin, Chang Hwan, Lee, Chi Young

Volltext

Corrigendum to “Augmentation of single-phase forced convection heat transfer in tightly arrayed rod bundle with twist-vane spacer grid” [Exp. Therm. Fluid Sci. 76 (2016) 185–192]... von Lee, Chi Young, In, Wang Kee, Lee, Jun Kyung

Volltext

Augmentation of single-phase forced convection heat transfer in tightly arrayed rod bundle with twist-vane spacer grid von Lee, Chi Young, In, Wang Kee, Lee, Jun Kyoung

Volltext