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Showing results 1 to 6 of 6

Issue DateTitleAuthor(s)TypeView
2016-08Crack growth behavior of warm-rolled 316L austenitic stainless steel in high-temperature hydrogenated waterChoi, Kyung-Joon; Yoo, Seung Chang; Jin, Hyung-Ha; Kwon, Junhyun; Choi, Min-Jae; Hwang, Seong Sik; Kim, Ji HyunARTICLE612
2018-06-19Irradiation creep behavior of iron base alloy at high temperature conditionChoi, Sang Il; Banisalman, Mosab; Lee, Gyeong-Geun; Kwon, Junhyun; Kim, Ji HyunCONFERENCE16
2014-06-15Modeling irradiation growth of zirconium and its alloy in nuclear reactorsChoi, Sang; Kim, Taeho; Shin, Sanghun; Lee, Gyeonggeun; Kwon, Junhyun; Kim, Ji HyunCONFERENCE12
2016-11Modeling of radiation-induced sink evolution in 6061 aluminum alloy in nuclear reactorsChoi, Sang Il; Lee, Gyeong-Geun; Kwon, Junhyun; Kim, Ji HyunARTICLE395
2016-01Modeling of sink-induced irradiation growth of single-crystal and polycrystal zirconiums in nuclear reactorsChoi,Sang Il; Lee, Gyeong-Geun; Kwon, Junhyun; Kim, Ji HyunARTICLE636
2020-08Using rate theory to better understand the stress effect of irradiation creep in iron and its based alloyChoi, Sang Il; Banisalman, Mosab Jaser; Lee, Gyeong-Geun; Kwon, Junhyun; Yoon, Eisung; Kim, Ji HyunARTICLE150
Showing results 1 to 6 of 6

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