Zobrazeno 1 - 10
of 119
pro vyhledávání: '"Suk Kwon Kim"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 12, Pp 4947-4950 (2024)
The blanket system is a crucial element in nuclear fusion power generation, tasked with tritium production and the efficient dissipation of the high thermal flux from the tokamak. Korea is in the process of developing the Helium Cooled Ceramic Reflec
Externí odkaz:
https://doaj.org/article/043d31d6f06c48f9ae383622d371caf3
Autor:
Chang Wook Shin, Seok-Kwon Son, Youngmin Lee, Suk-Kwon Kim, Hyung Gon Jin, Dong Won Lee, Mu-Young Ahn
Publikováno v:
Fusion Engineering and Design. 192:113716
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b76d9ef7034d393b0e60303e41624fda
https://doi.org/10.1016/j.fusengdes.2023.113716
https://doi.org/10.1016/j.fusengdes.2023.113716
Publikováno v:
IEEE Transactions on Plasma Science. 48:1501-1504
An advanced reduced activation alloy (ARAA) has been developed as a structural material for breeding blankets in fusion reactors. A breeding blanket has a relatively complex structure, so various welding methods, such as electron beam welding and sim
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b1b56c7f25900942b443b1b9cdd4142
https://doi.org/10.1109/tps.2020.2978813
https://doi.org/10.1109/tps.2020.2978813
Autor:
Hyoseong Gwon, Yi-Hyun Park, Jae-Sung Yoon, Suk-Kwon Kim, Youngmin Lee, Mu-Young Ahn, Seungyon Cho
Publikováno v:
Fusion Engineering and Design. 184:113280
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::80353cdd3632a0bfeb26d6873b9b86a1
https://doi.org/10.1016/j.fusengdes.2022.113280
https://doi.org/10.1016/j.fusengdes.2022.113280
Autor:
Hyung Gon Jin, Seok Kwan Lee, Suk-Kwon Kim, Doo-Hee Chang, Chang Wook Shin, Dong Won Lee, Sun Ho Kim, Bong-Ki Jung
Publikováno v:
Fusion Engineering and Design. 146:1419-1422
In accordance with the national fusion energy program of Korea, Korea Atomic Energy Research Institute (KAERI) has established a road map for the development of a volumetric fusion neutron source (V-FNS) and begun development of a compact fusion neut
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::96bb151f09d314b095b477b7f25b2b0b
https://doi.org/10.1016/j.fusengdes.2019.02.095
https://doi.org/10.1016/j.fusengdes.2019.02.095
Autor:
Dong Won Lee, Chang Wook Shin, Jae-Sung Yoon, Suk-Kwon Kim, Hyung Gon Jin, Eo Hwak Lee, Dong Jun Kim, Seong Dae Park
Publikováno v:
Fusion Engineering and Design. 136:1510-1513
KoHLT-EB (Korea Heat Load Test facility with Electron Beam gun) is operated for the performance qualification testing of the plasma facing components (PFC), ITER first wall (FW), ITER TBM (Test Blanket Module) FW, and DEMO PFCs in Korea. A thermal fa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::94fa37810b58b04e710006ed51d8b9c7
https://doi.org/10.1016/j.fusengdes.2018.05.044
https://doi.org/10.1016/j.fusengdes.2018.05.044
Autor:
Ji-Hyun Choi, Soon Chang Park, Hyung Gon Jin, Suk Kwon Kim, Dong Won Lee, Young-Bum Chun, Dong Jun Kim, Chang Shuk Kim, Seungyon Cho, Eo Hwak Lee, Kihak Im, Jae Sung Yoon, Cheol Woo Lee, Mu-Young Ahn, Seong Dae Park, Yi-Hyun Park, Duck Young Ku, Young-Min Lee
Publikováno v:
Fusion Engineering and Design. 136:190-198
Korea has own programs toward DEMO and fusion reactors that will require further improved DEMO blanket and energy utilization systems. Primary goals of DEMO blanket development in Korea are to develop and verify the integrated blanket design tools; t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9f655a9534ea37d1ccb93ea90bafd968
https://doi.org/10.1016/j.fusengdes.2018.01.050
https://doi.org/10.1016/j.fusengdes.2018.01.050
Autor:
Hyung Gon Jin, Jae Sung Yoon, Eo Hwak Lee, Seong Dae Park, Suk Kwon Kim, Dong Won Lee, Yang-Il Jung, Dong Jun Kim
Publikováno v:
IEEE Transactions on Plasma Science. 46:2663-2667
A helium cooled liquid lithium (or lead lithium) concept has been developed to design a liquid breeder blanket in South Korea. Ferritic–martensitic steel (FMS) was selected as a structural material for fusion reactors, and a commercial-scale advanc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3a156f24f80f248de21286900c14118d
https://doi.org/10.1109/tps.2018.2813308
https://doi.org/10.1109/tps.2018.2813308
Autor:
Soon Chang Park, Seungyon Cho, Jong-Il Kim, Eo Hwak Lee, Mu-Young Ahn, Bum Seok Kim, Young-Bum Chun, Seong Dae Park, Hyeong-Yeon Lee, Hyung Gon Jin, Dong Won Lee, Chang-Shuk Kim, Jae Sung Yoon, Young-Min Lee, Hyoseong Gwon, Suk-Kwon Kim, Duck Young Ku, Seok-Kwon Son, Cheol Woo Lee, Chang Wook Shin, Yi-Hyun Park, Sunghwan Yun
Publikováno v:
Fusion Engineering and Design. 171:112553
Development of the Helium Cooled Ceramic Reflector (HCCR) breeding blanket is underway according to the development strategy of core technology for K-DEMO under the fusion energy development roadmap in Korea. The main goals are to validate integrated
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7cdb822577ff2fde79ef597bf4157e89
https://doi.org/10.1016/j.fusengdes.2021.112553
https://doi.org/10.1016/j.fusengdes.2021.112553
Publikováno v:
Fusion Engineering and Design. 124:774-778
Korea has designed a helium cooled ceramic reflector (HCCR) test blanket module (TBM) that includes a TBM shield, called a TBM set, that will be tested in ITER. The HCCR TBM is composed of four sub-modules and a back manifold. In addition, each sub-m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b3c48e35d210ba063b45805d4e960078
https://doi.org/10.1016/j.fusengdes.2017.04.046
https://doi.org/10.1016/j.fusengdes.2017.04.046