Zobrazeno 1 - 10
of 133
pro vyhledávání: '"Yun-Soo Lim"'
Autor:
Hong-Pyo Kim, Jong-Yeon Lee, Sung-Hwan Cho, Min-Jae Choi, Sung-Woo Kim, Hyung-Ha Jin, Dong-Jin Kim, Seoung-Sik Hwang, Yun-Soo Lim
Publikováno v:
Archives of Metallurgy and Materials, Vol vol. 69, Iss No 1, Pp 49-52 (2024)
Fractography of stress corrosion cracking (SCC) of 20% cold worked Type 304 H stainless steel containing δ-ferrite was studied using a compact tension (CT) specimen in oxidizing primary water with a scanning electron microscope (SEM) and electron ba
Externí odkaz:
https://doaj.org/article/349344bf520848d9a79fb6e5c74d929a
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
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 4, Pp 1060-1068 (2019)
This work aims to establish a model of a primary water stress corrosion crack growth rate of Alloy 690 material for the head penetration nozzles of Korean pressurized water reactors. The test material had an inhomogeneous microstructure with bands of
Externí odkaz:
https://doaj.org/article/341c20d20a90408f8155f99cd70238f9
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 51, Iss 1, Pp 228-237 (2019)
The crack growth responses of as-received and as-welded Alloy 600/182 and Alloy 690/152 welds to constant loading were measured by a direct current potential drop method using compact tension specimens in primary water at 325 °C simulating the norma
Externí odkaz:
https://doaj.org/article/459cd0db4a224d58847be7170d47367a
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 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
Autor:
Woo Hyuk Choi, Yun-Soo Lim, Min Suk Kim, Hyungsun Kim, Sung Min So, Jongee Park, Kyoung Hun Kim, Joo Seok Park
Publikováno v:
Ceramics International. 46:9575-9581
We fabricated boron carbide-silicon carbide (B4C–SiC) composites by hot-press sintering without additives and evaluated the crystal phase, relative density, microstructure, and mechanical properties of the sintered body. When B4C and SiC were unifo
Publikováno v:
Materials Characterization. 194:112445