Zobrazeno 1 - 10
of 183
pro vyhledávání: '"J.S. Bak"'
Autor:
Sergio Orlandi, S. Chiocchio, Andreas Lee, Yasuhiro Iwata, G. Rigoni, Jean-Jacques Cordier, I. Kuehn, Miikka Kotamaki, Leontin Carafa, Romaric Darbour, Alain Baudry, Thomas Jeannoutot, J. Reich, Rachel Packer, J.S. Bak, Joelle Elbez, Magali Benchikhoune, B. Levesy, Simon Sweeney, Laurent Patisson, Giovanni di Giuseppe
Publikováno v:
Fusion Engineering and Design. :240-243
The ITER Tokamak complex consists of Tokamak, diagnostic and tritium buildings. The Tokamak machine is located in the bioshield pit of the Tokamak building. Plant systems are implemented in the three buildings and are strongly interfacing with the To
Autor:
H.G. Kim, H.J. Sung, Y.J. Lee, Yung-Jin Jung, T.S. Kim, Byung-Chul Kim, K.H. Park, K.H. Hong, J.S. Bak, J.W. Sa, Hyun-Chul Kim, Il Keun Kwon, K.J. Jung, J.S. Lee, Byeong-hee Roh, T.H. Kwon, S.Y. Choi, Hee-Jae Ahn, C.K. Park
Publikováno v:
Fusion Engineering and Design. 88:1960-1964
As a participant of ITER project, ITER Korea has to supply two ITER vacuum vessel sectors (Sector #6, #1) of total nine ITER VV sectors. After the procurement arrangement with ITER Organization, ITER Korea made the contract with Hyundai Heavy Industr
Autor:
X. Wang, G.W. Yun, H.J. Ahn, H.H. Bae, I.T. Bae, B.C. Kim, H.S. Kim, Chang-Hwan Choi, J.W. Sa, K. Ioki, J.S. Bak
Publikováno v:
Fusion Engineering and Design. 87:1055-1059
The ITER neutral beam port is composed of connecting duct, port extension and port stub extension. The spaces between inner and outer shells of the port extension and port stub extension are filled with pre-assembled blocks, called in-wall shielding.
Publikováno v:
Fusion Engineering and Design. 87:921-926
Since the recommendation of blanket redesign by 2007 ITER design review, the blanket system has been developed in the framework of Blanket Integrated Product Team (BIPT) composed mainly of ITER organization (IO) and procuring parties. After the compl
Publikováno v:
Fusion Engineering and Design. 87:1079-1084
The ITER vacuum vessel gravity supports located in the lower level shall sustain loads in radial, toroidal and vertical directions. The hinge type VVGS consists of two hinges, upper and lower blocks and dowels. In order to develop the design concept
Autor:
C. Bachmann, H.J. Ahn, B.Y. Kim, M.S. Ha, X. Wang, J.S. Bak, J.W. Sa, Y.K. Kim, H.S. Kim, B.C. Kim, K. Ioki, Chang-Hwan Choi
Publikováno v:
Fusion Engineering and Design. 86:2003-2007
In order to verify design feasibility and structural integrity of a hinge type support for the ITER VV support system, the design analysis has been performed in detail, which includes heat transfer, elastic stress and limit analyses. The structural a
Autor:
K.J. Jung, H. J. Ahn, B.C. Kim, J. Yu, Chang Hyun Noh, Y. Utin, J.S. Bak, K. Ioki, Kwanwoo Nam, Namil Her, W. Chung
Publikováno v:
Fusion Engineering and Design. 85:1866-1874
The detailed design of ITER thermal shield (TS), which is planned to be procured completely by Korea, has been implemented since 2007. In this paper, the design and the supporting analysis are described for the critical components of the TS, the vacu
Publikováno v:
Fusion Engineering and Design. 85:2217-2221
The Republic of Korea is participating in the ITER project as a full member and procuring components for the ITER tokamak and its facility. This paper presents the current stage of preparation of the ITER components to be delivered by Korea including
Autor:
B.C. Kim, Namil Her, W. Chung, Chang Hyun Noh, Y. Utin, J. Yu, Dong Kwon Kang, Kwanwoo Nam, K. Ioki, J.S. Bak, K.J. Jung, H. J. Ahn
Publikováno v:
Fusion Engineering and Design. 85:1880-1884
ITER thermal shield, which is to be fully made by Korea, is very large system and its tolerance requirement is so tight that the precise design and manufacture are indispensable. Therefore, it is very important that the critical components of the the
Autor:
B.Y. Kim, H.S. Kim, F. Geli, M. Urbani, Y.K. Kim, M.H. Han, J.S. Bak, B.C. Kim, H.J. Jung, C.D. Hong, J.S. Lee, H.J. Ahn, J.W. Sa
Publikováno v:
Fusion Engineering and Design. 85:2207-2212
Recently the new concept of the ITER neutral beam (NB) duct liner has been developed to improve thermo-mechanical performance and satisfy the requirements for remote handling and maintenance. The design concept of cooling module located inside neutro