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Crack growth behavior of warm-rolled 316L austenitic stainless steel in high-temperature hydrogenated water File

Choi, Kyung-Joon , Yoo, Seung Chang , Jin, Hyung-Ha , Kwon, Junhyun , Choi, Min-Jae , Hwang, Seong Sik , Kim, Ji Hyun

Article Issue Date2016-08 View42
Irradiation creep behavior of iron base alloy at high temperature condition

Choi, Sang Il , Banisalman, Mosab , Lee, Gyeong-Geun , Kwon, Junhyun , Kim, Ji Hyun

Conference Paper Issue Date2018-06-19 View29
Modeling irradiation growth of zirconium and its alloy in nuclear reactors

Choi, Sang , Kim, Taeho , Shin, Sanghun , Lee, Gyeonggeun , Kwon, Junhyun , Kim, Ji Hyun

Conference Paper Issue Date2014-06-15 View35
Modeling of radiation-induced sink evolution in 6061 aluminum alloy in nuclear reactors File

Choi, Sang Il , Lee, Gyeong-Geun , Kwon, Junhyun , Kim, Ji Hyun

Article Issue Date2016-11 View58
Modeling of sink-induced irradiation growth of single-crystal and polycrystal zirconiums in nuclear reactors File

Choi,Sang Il , Lee, Gyeong-Geun , Kwon, Junhyun , Kim, Ji Hyun

Article Issue Date2016-01 View44
Using rate theory to better understand the stress effect of irradiation creep in iron and its based alloy File

Choi, Sang Il , Banisalman, Mosab Jaser , Lee, Gyeong-Geun , Kwon, Junhyun , Yoon, Eisung , Kim, Ji Hyun

Article Issue Date2020-08 View77
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