Zobrazeno 1 - 10
of 122
pro vyhledávání: '"SEONG SIK HWANG"'
Autor:
Dong-Jin Kim, Sung-Woo Kim, Jong Yeon Lee, Kyung Mo Kim, Se Beom Oh, Gyeong Geun Lee, Jongbeom Kim, Seong-Sik Hwang, Min Jae Choi, Yun Soo Lim, Sung Hwan Cho, Hong Pyo Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 3003-3011 (2021)
A FAC (flow-accelerated corrosion) test was performed for a straight pipe composed of the SA335 Gr P22 and SA106 Gr B (SA106-SA335-SA106) types of steel with welds as a function of the flow rate in the range of 7–12 m/s at 150 °C and with DO
Externí odkaz:
https://doaj.org/article/3f7ccc58509f465bbb4097c6b20fd253
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 6, Pp 1222-1230 (2020)
The corrosion rates of the reactor pressure vessel materials of SA508 Grade 3 were measured using a weight loss method in aerated boric acid solutions to simulate the evaporation of leaked PWR primary water in an ambient environment. The corrosion be
Externí odkaz:
https://doaj.org/article/839804ca9d1241aaa1604a16a85cd800
Autor:
Hong-Pyo Kim, Yun-Min Park, Hyoung-Min Jang, Sang-Yeob Lim, Min-Jae Choi, Sung-Woo Kim, Dong-Jin Kim, Seong-Sik Hwang, Yun-Soo Lim
Publikováno v:
Metals, Vol 12, Iss 11, p 1794 (2022)
The early-stage M23C6 morphology at the phase boundary between austenite and δ ferrite grain in Type 304L austenitic stainless steel was investigated with transmission electron microscopy (TEM). The M23C6 has coherency with austenite grains at phase
Externí odkaz:
https://doaj.org/article/8f84e7d8780c4aa98267c7ad86376484
Autor:
Sung Hwan Cho, Jong Yeon Lee, Sung-Woo Kim, Se Beom Oh, Jongbeom Kim, Seong-Sik Hwang, Min Jae Choi, Gyeong Geun Lee, Kyung Mo Kim, Dong-Jin Kim, Hong Pyo Kim, Yun Soo Lim
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 3003-3011 (2021)
A FAC (flow-accelerated corrosion) test was performed for a straight pipe composed of the SA335 Gr P22 and SA106 Gr B (SA106-SA335-SA106) types of steel with welds as a function of the flow rate in the range of 7–12 m/s at 150 °C and with DO
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::67c6717b7f0d918d2436146c8b2e614b
https://doi.org/10.1016/j.net.2021.03.026
https://doi.org/10.1016/j.net.2021.03.026
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 1, Pp 67-72 (2013)
Stress corrosion cracking (SCC) behaviors of Alloy 690 were studied in lead-containing aqueous alkaline solutions using the slow strain rate tension (SSRT) tests in 0.1M and 2.5M NaOH with and without PbO at 315°C. The side and fracture surfaces of
Externí odkaz:
https://doaj.org/article/be0d176884e6412685ee6041d25c8423
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 1, Pp 73-80 (2013)
The primary water stress corrosion cracking (PWSCC) of Alloy 600 in a PWR has been reported in the control rod drive mechanism (CRDM), pressurizer instrumentation, and the pressurizer heater sleeves. Recently, two cases of boric acid precipitation th
Externí odkaz:
https://doaj.org/article/376c25a51dc74f5c9b96ff98df9c34a6
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 6, Pp 1222-1230 (2020)
The corrosion rates of the reactor pressure vessel materials of SA508 Grade 3 were measured using a weight loss method in aerated boric acid solutions to simulate the evaporation of leaked PWR primary water in an ambient environment. The corrosion be
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::be5715af338e5bc85f8c83ddf2ed45fb
https://doi.org/10.1016/j.net.2019.11.031
https://doi.org/10.1016/j.net.2019.11.031
Publikováno v:
Korean Journal of Dental Materials. 46:185-194
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5ce2ea5e2fb7d9ef6f876f45de0cd639
https://doi.org/10.14815/kjdm.2019.46.4.185
https://doi.org/10.14815/kjdm.2019.46.4.185
Publikováno v:
Materials Characterization. 194:112445
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a05fd6b0d58fa6faa1bd478c99f9e86
https://doi.org/10.1016/j.matchar.2022.112445
https://doi.org/10.1016/j.matchar.2022.112445
Publikováno v:
Journal of Nuclear Materials. 513:271-281
We report on microstructural and mechanical property changes as a function of radiation damage value in proton-irradiated austenitic stainless steel by means of advanced characterization techniques. The microstructural changes in proton-irradiated au
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0cd431cf662447f5979f841ccfee373e
https://doi.org/10.1016/j.jnucmat.2018.11.017
https://doi.org/10.1016/j.jnucmat.2018.11.017