Zobrazeno 1 - 10
of 103
pro vyhledávání: '"SEONG SIK HWANG"'
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
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
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
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
Publikováno v:
Korean Journal of Dental Materials. 46:185-194
Publikováno v:
Materials Characterization. 194:112445
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
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 7, Pp 1131-1137 (2018)
The effect of a serrated grain boundary on stress corrosion cracking (SCC) of Alloy 600 was investigated in terms of improvement of SCC resistance. Serrated grain boundaries and straight grain boundaries were obtained by controlled heat treatment. SC