Corrigendum to “Heat-transfer characteristics of screw tube in one-side high heat load condition for fusion reactor divertor application”[Int. J. Adv. Nucl. Reactor. Des. Technol. 3 (2021) 213–225]
Ji Hwan Lim,
Su Won Lee,
Hoongyo Oh,
Minkyu Park,
Donkoan Hwang,
Moo Hwan Kim,
HangJin Jo
Affiliations
Ji Hwan Lim
Division of Advanced Nuclear Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea
Su Won Lee
Division of Advanced Nuclear Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea
Hoongyo Oh
Department of Mechanical Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea
Minkyu Park
Division of Advanced Nuclear Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea
Donkoan Hwang
Division of Advanced Nuclear Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea
Moo Hwan Kim
Division of Advanced Nuclear Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea; Department of Mechanical Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea
HangJin Jo
Division of Advanced Nuclear Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea; Department of Mechanical Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea; Corresponding author. Division of Advanced Nuclear Engineering, POSTECH, Hyoja-dong, Nam-gu, Pohang, Kyung-buk, South Korea.
