Experimental evaluation of local bubble parameters of subcooled boiling flow in a pressurized vertical annulus channel
Chu, In-Cheol, Lee, Seung-Jun, Youn, Young Jung, Park, Jong Kuk, Choi, Hae Seob, Euh, Dong-Jin, Song, Chul-Hwa
Published in Nuclear engineering and design (01.02.2017)
Published in Nuclear engineering and design (01.02.2017)
Get full text
Journal Article
Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor
Chang, Seok-Kyu, Euh, Dong-Jin, Choi, Hae Seob, Kim, Hyungmo, Choi, Sun Rock, Lee, Hyeong-Yeon
Published in Nuclear engineering and technology (01.04.2016)
Published in Nuclear engineering and technology (01.04.2016)
Get full text
Journal Article
Contribution of thermal–hydraulic validation tests to the standard design approval of SMART
Park, Hyun-Sik, Kwon, Tae-Soon, Moon, Sang-Ki, Cho, Seok, Euh, Dong-Jin, Yi, Sung-Jae
Published in Nuclear engineering and technology (01.10.2017)
Published in Nuclear engineering and technology (01.10.2017)
Get full text
Journal Article
On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes
Kim, Jong-Bum, Jeong, Ji-Young, Lee, Tae-Ho, Kim, Sungkyun, Euh, Dong-Jin, Joo, Hyung-Kook
Published in Nuclear engineering and technology (01.10.2016)
Published in Nuclear engineering and technology (01.10.2016)
Get full text
Journal Article
Quantitative observation of co-current stratified two-phase flow in a horizontal rectangular channel
Lee, Seungtae, Euh, Dong-Jin, Kim, Seok, Song, Chul-Hwa
Published in Nuclear engineering and technology (01.04.2015)
Published in Nuclear engineering and technology (01.04.2015)
Get full text
Journal Article
An Experimental Evaluation of the APR1000 Core Flow Distribution Using a 1/5 Scale Model
Kim, Kihwan, Kim, Woo-Shik, Choi, Hae-Seob, Seol, Hyosung, Lim, Byung-Jun, Euh, Dong-Jin
Published in Energies (Basel) (01.06.2024)
Published in Energies (Basel) (01.06.2024)
Get full text
Journal Article
On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes
Kim, Jong-Bum, Jeong, Ji-Young, Lee, Tae-Ho, Kim, Sungkyun, Euh, Dong-Jin, Joo, Hyung-Kook
Published in Nuclear engineering and technology (2016)
Get full text
Published in Nuclear engineering and technology (2016)
Journal Article