Zobrazeno 1 - 10
of 53
pro vyhledávání: '"Hyung Ha Jin"'
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
Publikováno v:
Heliyon, Vol 10, Iss 15, Pp e34935- (2024)
This study explores the microstructural characteristics of gadolinium (Gd)-rich phases in titanium (Ti) alloys through comprehensive electron microscopy analysis. The Ti alloys were produced using plasma arc melting and subsequently hot-forged. Elabo
Externí odkaz:
https://doaj.org/article/86872011062a4df6be8ebc028c797754
Autor:
Sangeun Kim, Minkyu Ahn, Jinwoo Park, Gyeongsik Yu, Jinhyuk Kim, Hyung-Ha Jin, Chang-hoon Lee, Byung-Yong Yu, Weon Cheol Lim, Chansun Shin
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101652- (2024)
This study explores the effects of Fe ion irradiation and helium implantation on the mechanical and microstructural behaviors of K-RAFM steels. Through micropillar compression tests, we observed irradiation hardening, which manifested as an increase
Externí odkaz:
https://doaj.org/article/8e0f505415c2474da2dc487a0b7fed19
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 4042-4051 (2021)
abstract: In this work, we applied a multilevel modeling technique to estimate the diametral creep in the pressure tubes of Korean Canada Deuterium Uranium (CANDU) units. Data accumulated from in-service inspections were used to develop the model. To
Externí odkaz:
https://doaj.org/article/6343ea8ec16b4779a9b76120b5650a3d
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 3, Pp 915-921 (2019)
Radiation damage due to neutrons has been calculated in Ni-based alloys in Wolsong CANDU reactor environments. Two damage parameters are considered: displacement damage, and transmutation gas production. We used the SPECTER and SRIM computer codes in
Externí odkaz:
https://doaj.org/article/49e4b1b7f8f14238980d536ed6229d7c
Autor:
Seongin Moon, To Kang, Soonwoo Han, Kyung-Mo Kim, Hyung-Ha Jin, Sung-Woo Kim, Munsung Kim, Hyunil Seo
Publikováno v:
Applied Sciences, Vol 11, Iss 19, p 8888 (2021)
Traditional ultrasonic imaging methods have a low accuracy in the localization of defects in austenitic welds because the anisotropy and inhomogeneity of the welds cause distortion of the ultrasonic wave propagation paths in anisotropic media. The di
Externí odkaz:
https://doaj.org/article/5135b16b376a44dcad8ce761ec9a5106
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 4042-4051 (2021)
In this work, we applied a multilevel modeling technique to estimate the diametral creep in the pressure tubes of Korean Canada Deuterium Uranium (CANDU) units. Data accumulated from in-service inspections were used to develop the model. To confirm t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6409bf6d5b478608bd501caa7e63fac1
http://www.sciencedirect.com/science/article/pii/S1738573321003405
http://www.sciencedirect.com/science/article/pii/S1738573321003405
Autor:
Seong-Yong Cho, Chang-Hoon Lee, Joonoh Moon, Hyung Ha Jin, Sangeun Kim, Jungwoo Heo, Hyeongchul Kim, Chansun Shin
Publikováno v:
Journal of the Korean Physical Society. 77:32-37
Surface swelling caused by He implantation was studied for newly-developed Ti/Ta-added reduced-activation ferritic/martensitic (RAFM) steels. Post-implantation annealing at 623 K for 2 h of He-implanted RAFM-steel samples led to surface-step formatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7a9ff1798082d043f84714896e03c27e
https://doi.org/10.3938/jkps.77.32
https://doi.org/10.3938/jkps.77.32
Publikováno v:
Materials Characterization. 194:112364
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0a4d4e6eb510a4cca5438a788954b26c
https://doi.org/10.1016/j.matchar.2022.112364
https://doi.org/10.1016/j.matchar.2022.112364
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 3, Pp 915-921 (2019)
Radiation damage due to neutrons has been calculated in Ni-based alloys in Wolsong CANDU reactor environments. Two damage parameters are considered: displacement damage, and transmutation gas production. We used the SPECTER and SRIM computer codes in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::540c08fdf64f82d47fa05f5628f30f0b
https://doi.org/10.1016/j.net.2018.11.015
https://doi.org/10.1016/j.net.2018.11.015