Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Hakkun Kim"'
Autor:
Yungjin Jung, Hyun-Soo Kim, Hokyu Moon, Juyeon Han, Hakkun Kim, Jeongwoo Sa, Yunseok Hong, Juntao Jing, Sesub Hwang, Jongbae Kim, Youngmin Ham, Kihwan Moon, Junhyuk Jeon, Soohyun Jang, Seong J. Cho
Publikováno v:
Fusion Engineering and Design. 193:113644
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4203ac2e6c4f350e29f382495bd9f821
https://doi.org/10.1016/j.fusengdes.2023.113644
https://doi.org/10.1016/j.fusengdes.2023.113644
Autor:
J. Bousquet, Bertrand Peluso, Hakkun Kim, S. Bremond, G. Jiolat, Y. Ilyin, P. Decool, O. Dumoulin, T. Brilleman, T. Lamiral
Publikováno v:
Fusion Engineering and Design. 146:543-546
The ITER magnet system will be the largest superconducting magnet system ever built. The system, all inside a cryostat, is mainly composed of a Central Solenoid (CS) split in 6 modules, a set of 18 Toroidal Field (TF) d -shaped coils and 6 Poloidal F
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::383049e8a0abf6c2e9f8fb51dd0a3014
https://doi.org/10.1016/j.fusengdes.2019.01.018
https://doi.org/10.1016/j.fusengdes.2019.01.018
Autor:
Hyun-Chul Kim, Chulkyu Park, Hokyu Moon, Wooho Chung, J.W. Sa, Hakkun Kim, Bong Gook Kang, Jason Cheon, J.S. Lee, Yu-Gyeong Kim, Gwang-Ho Kim
Publikováno v:
Fusion Engineering and Design. 146:598-602
The Factory Acceptance Test (FAT) for ITER components should be complied with the RCC-MR 2007 code and French regulations of nuclear pressure equipment (ESPN) to assure quality of nuclear pressure equipment. The procedure of FAT for lower port has be
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0bca831d79cdc804ce857a9d8c705077
https://doi.org/10.1016/j.fusengdes.2019.01.032
https://doi.org/10.1016/j.fusengdes.2019.01.032
Autor:
K. Saito, Tetsuo Seki, Takashi Mutoh, Shuji Kamio, Ryosuke Seki, Hiroshi Kasahara, Goro Nomura, Hakkun Kim, S.J. Wang, H.H. Wi
Publikováno v:
Fusion Engineering and Design. 146:256-260
In the Large Helical Device (LHD), the development of high-power and long-pulse Ion Cyclotron Range of Frequencies (ICRF) heating system is ongoing. The developed Field-Aligned-Impedance-Transforming (FAIT) antenna has the potential for high-power in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bb114af01fb0b1c24963a46054cc4b42
http://hdl.handle.net/10655/00012600
http://hdl.handle.net/10655/00012600
Autor:
Hyun-Soo Kim, Yu-Gyeong Kim, Gwang-Ho Kim, Kwen-Hee Hong, Chulkyu Park, Wooho Chung, Hokyu Moon, J.W. Sa, Hakkun Kim
Publikováno v:
Fusion Engineering and Design. 136:1514-1517
The procedure of factory acceptance test for ITER vacuum vessel lower port stub extension has been set to that visual test, pressure test, baking, vacuum leak test, and final dimensional inspection as listed order. Among them, the pressure test and t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ccf020ca54a8989471f8a2962daf6cb
https://doi.org/10.1016/j.fusengdes.2018.05.045
https://doi.org/10.1016/j.fusengdes.2018.05.045
Publikováno v:
Fusion Engineering and Design. 126:67-72
Non-inductive current drive by fast wave at very high ion cyclotron harmonics, known as ‘helicons’ has the potential for high off-axis current drive efficiency compared with the other known non-inductive current drive techniques. However, non-ind
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b0a18d07d1f0533bec339c7d502a122
https://doi.org/10.1016/j.fusengdes.2017.11.016
https://doi.org/10.1016/j.fusengdes.2017.11.016
Autor:
Hakkun Kim, Nam-Yong Jung, JaeIn Song, Yeong-Kook Oh, KunSu Lee, H. Y. Lee, Suk-Ho Hong, Kwang-Pyo Kim, Kaprai Park, Yong Chu
Publikováno v:
Fusion Engineering and Design. :1515-1518
Efforts have been made to obtain vacuum condition that is essential for the plasma experiments. Under certain situations, for example, the vacuum vessel should be vented to repair in-vessel components such as diagnostic shutter, exchange of window fo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c7b161a509b27388b65e482032a2ce04
https://doi.org/10.1016/j.fusengdes.2015.07.001
https://doi.org/10.1016/j.fusengdes.2015.07.001
Publikováno v:
Fusion Engineering and Design. :1276-1280
The heat flux in KSTAR is estimated for various discharge conditions by using thermocouple arrays. The heat flux on the divertor is higher than that on inboard limiter or passive stabilizer by a factor of 2. Although the plasma configuration in KSTAR
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f8ae36a727d96aaccdbe9624c94d6e46
https://doi.org/10.1016/j.fusengdes.2015.02.013
https://doi.org/10.1016/j.fusengdes.2015.02.013
Autor:
KunSu Lee, Eunnam Bang, Hyunglyul Yang, Suk-Ho Hong, Hakkun Kim, Yaowei Yu, Hong-Tack Kim, Kyungmin Kim
Publikováno v:
Fusion Engineering and Design. 88:1744-1748
KSTAR has reached a plasma current up to 630 kA, plasma duration up to 12 s, and has achieved high confinement mode (H-mode) in 2011 campaign. The heat flux of PFC tile was estimated from the temperature increase of PFC since 2010. The heat flux of P
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7ba7633bbdf3696b25acc4da334ae1a4
https://doi.org/10.1016/j.fusengdes.2013.04.045
https://doi.org/10.1016/j.fusengdes.2013.04.045