Zobrazeno 1 - 10
of 73
pro vyhledávání: '"Kwanwoo Nam"'
Publikováno v:
Fusion Engineering and Design. 146:2509-2513
Thermal Shield (TS) in ITER tokamak reduces heat loads from vacuum vessel and cryostat to superconducting magnet structure. Unlike to other components in ITER tokamak, most of TS have slender structure with panel thickness of 20 mm. Due to its struct
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1892ac24f37fd168a2437f5ea1884048
https://doi.org/10.1016/j.fusengdes.2019.04.030
https://doi.org/10.1016/j.fusengdes.2019.04.030
Autor:
Nam Il Her, Terenig Arzoumanian, Chang Hyun Noh, Kwanwoo Nam, Flavien Sabourin, Chang Ho Choi, Dongkwon Kang, Naresh Gupta, Manoj Panchal, Germán Pérez-Pichel, J.-M. Martinez, Shyam P. Singh
Publikováno v:
Fusion Engineering and Design. 146:2302-2306
This paper aims to provide a comprehensiveness description of the ITER Thermal Shield thermal integrity management keeping focused on the methods required for supporting the Thermal Shield manufacturing and assembly phases. Three main aspects are cov
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b671f6e7e9b6e5ac626ae04593a7370
https://doi.org/10.1016/j.fusengdes.2019.03.177
https://doi.org/10.1016/j.fusengdes.2019.03.177
Autor:
Namil Her, Dong Kwon Kang, Kwanwoo Nam, Kyoung-O Kang, Chang Hyun Noh, Junyoung Hur, Kyoungkyu Kim
Publikováno v:
Fusion Engineering and Design. 146:1533-1538
The main components of the ITER tokamak are assembled from the nine sub-assemblies of the 40° sectors. During the sub-assembly, the Toroidal Field coils (TFCs) are installed outside of the Vacuum Vessel Thermal Shield (VVTS) by rotation. The clearan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::293824d9340a13f9c2577df420f96013
https://doi.org/10.1016/j.fusengdes.2019.02.122
https://doi.org/10.1016/j.fusengdes.2019.02.122
Autor:
Kyoung-O Kang, Kisuk Lim, Dong Kwon Kang, Kwanwoo Nam, Youngkil Kang, Namil Her, Terenig Arzoumanian, German Perez Pichel, Manoj Panchal, Junyoung Hur, Il Jin Kim, Won Woo Park, Chang Hyun Noh
Publikováno v:
Fusion Engineering and Design. 146:1171-1175
This paper describes the manufacturing study of ITER Lower Cryostat Thermal Shield (LCTS) cylinder components, which are to be delivered to ITER site. All LCTS cylinder 20 ° sectors will be assembled at the ITER site by the flange joints, which are
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae1c6f973e3ed0ed5ab006d7b0123dcc
https://doi.org/10.1016/j.fusengdes.2019.02.034
https://doi.org/10.1016/j.fusengdes.2019.02.034
Publikováno v:
Fusion Engineering and Design. 136:752-758
Flow distribution on the piping network of ITER Thermal Shield (TS) is analyzed and orifice installation is suggested for attenuating flow mal-distribution. Flow test is performed for a TS segment to verify the analysis model. Room temperature nitrog
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3038821407faf3e287d79b3a08fe5192
https://doi.org/10.1016/j.fusengdes.2018.04.004
https://doi.org/10.1016/j.fusengdes.2018.04.004
Autor:
Namil Her, Wooho Chung, Chang Hyun Noh, Chang Ho Choi, Kyoung-O Kang, Kisuk Lim, German Perez Pichel, Hyeon Gon Lee, Manoj Panchal, Dong Kwon Kang, Kwanwoo Nam, Youngkil Kang, Ki-Jung Jung
Publikováno v:
Fusion Engineering and Design. 134:132-136
This paper describes the manufacturing progress of ITER Vacuum Vessel Thermal Shield (VVTS) sectors, which are on-going since the start of material buffing in October 2014. Fabrication of VVTS proceeds according to the following main processes: 1) pl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::28a6699bc2f403c175d64d8a2052a93b
https://doi.org/10.1016/j.fusengdes.2018.01.056
https://doi.org/10.1016/j.fusengdes.2018.01.056
Autor:
Dong Kwon Kang, Perez Pichel German, Kwanwoo Nam, Il Jin Kim, Namil Her, Chang Hyun Noh, Panchal Manoj, Kisuk Lim, Yong-Hee Lee, Won Woo Park, Junyoung Hur, Kyoung-O Kang
Publikováno v:
Fusion Engineering and Design. 172:112777
ITER Thermal Shield (TS) reduces radiation heat loads from vacuum vessel and cryostat to superconducting magnet structure. One of the key process among the fabrication of TS is the silver electroplating to reduce the emissivity. Requirement on emissi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5e1d757bf087e54a0000dd6d711dda5b
https://doi.org/10.1016/j.fusengdes.2021.112777
https://doi.org/10.1016/j.fusengdes.2021.112777
Autor:
Panchal Manoj, Il Jin Kim, Kisuk Lim, Chang Hyun Noh, Chulsoon Shin, Yong-Hee Lee, Won Woo Park, Junyoung Hur, Perez Pichel German, Namil Her, Dong Kwon Kang, Kwanwoo Nam, Kyoung-O Kang
Publikováno v:
Fusion Engineering and Design. 165:112270
In the ITER tokamak, a thermal shield (TS) is installed to reduce the heat oad radiated to the superconducting magnet system from vacuum vessel (VV) and cryostat. TS has a thin silver surface to keep its emissivity below 0.05. The silver surface is a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1973a0c1c654edefe452819b26abdb42
https://doi.org/10.1016/j.fusengdes.2021.112270
https://doi.org/10.1016/j.fusengdes.2021.112270
Autor:
Robin Le Barbier, Gyoung-O. Kang, Robby Hick, Chang Ho Choi, C. Sborchia, Terenig Arzoumanian, Wooho Chung, Dong Kwon Kang, Kwanwoo Nam, Youngkil Kang, Chang Hyun Noh, Kisuk Lim, Namil Her
Publikováno v:
Fusion Engineering and Design. :937-941
The role of the ITER Thermal Shields (TS) is to minimize the radiation heat load from the warm components such as vacuum vessel and cryostat to magnet operating at 4.5 K. The final design of TS was completed in 2013 and manufacturing of the vacuum ve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7632d983c7057b2a131deb008bbba30c
https://doi.org/10.1016/j.fusengdes.2016.01.050
https://doi.org/10.1016/j.fusengdes.2016.01.050
Autor:
D.C. Yoon, Kisuk Lim, Kwanwoo Nam, R.G. Kim, Wooho Chung, Chang Hyun Noh, Dongkwon Kang, J.P. Baek
Publikováno v:
Fusion Engineering and Design. :817-823
This paper describes both the test results of the bath type silver coating and the design of the bath to construct the silver coating plant for ITER thermal shield. The tests of small specimens made of SS304L and SS304LN were carried out to investiga
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::31b8af364131e3cd071ead2280f0bd19
https://doi.org/10.1016/j.fusengdes.2016.01.069
https://doi.org/10.1016/j.fusengdes.2016.01.069