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Bae, J. W.*; Jung, J.*; Kim, J. G.*; Park, J. M.*; Harjo, S.; Kawasaki, Takuro; Woo, W.*; Kim, H. S.*
Materialia, 9, p.100619_1 - 100619_15, 2020/03
Jung, W.*; Ahn, J. K.*; Hasegawa, Shoichi; Hicks, K.*; Hwang, S.*; Ichikawa, Yudai; Kim, S.*; Sako, Hiroyuki; Sato, Susumu; Tanida, Kiyoshi
JPS Conference Proceedings (Internet), 27, p.011007_1 - 011007_6, 2019/11
Kojima, Atsushi; Hanada, Masaya; Jeong, S. H.*; Bae, Y. S.*; Chang, D. H.*; Kim, T. S.*; Lee, K. W.*; Park, M.*; Jung, B. K.*; Mogaki, Kazuhiko; et al.
Fusion Engineering and Design, 102, p.81 - 87, 2016/01
Times Cited Count：6 Percentile：43.97(Nuclear Science & Technology)The long-pulse acceleration of the high-power positive ion beam has been demonstrated with the JT-60 positive ion source in the joint experiment among Japan Atomic Energy Agency (JAEA), Korea Atomic Energy Research Institute (KAERI) and National Fusion Research Institute (NFRI) under the collaboration program for the development of plasma heating and current drive systems. As a result of development of the operation techniques of the ion source and facilities of the neutral beam test stand in KAERI, 2 MW 100 s beam has been achieved for the first time. The achieved beam performance satisfies the JT-60SA requirement which is designed to be a 1.94 MW ion beam power from an ion source corresponding to total neutral beam power of 20 MW with 24 ion sources. Therefore, it was found that the JT-60 positive ion sources were applicable in the JT-60SA neutral beam injectors without further modification of the ion source and the accelerator. Moreover, because this ion source is planned to be a backup ion source for KSTAR, the operational region and characteristic has been clarified to apply to the KSTAR neutral beam injector.
Vostner, A.*; Pong, I.*; Bessette, D.*; Devred, A.*; Sgobba, S.*; Jung, A.*; Weiss, K.-P.*; Jewell, M. C.*; Liu, S.*; Yu, W.*; et al.
IEEE Transactions on Applied Superconductivity, 23(3), p.9500705_1 - 9500705_5, 2013/06
Times Cited Count：13 Percentile：53.13(Engineering, Electrical & Electronic)The ITER Cable-In-Conduit Conductor (CICC) used in the superconducting magnet system consists of a cable made of 300 to 1440 strands housed in a stainless steel tube (a.k.a. jacket or conduit). There are circular, square, as well as circle-in-square jackets, made of either a very low carbon AISI 316LN grade stainless steel or a high Mn austenitic stainless steel developed for ITER called JK2LB. Selected mechanical properties of the base material and weld joint were tested at room temperature and/or cryogenic temperatures (
7 K). The Domestic Agencies (DAs) reference laboratories and the ITER-IO appointed reference laboratories, CERN and Karlsruhe Institute of Technology (KIT) performed mechanical tests. This paper will compare the test results (e.g. elongation to failure) from different laboratories.
Shibata, Taiju; Sumita, Junya; Makita, Taiyo*; Takagi, Takashi*; Kunimoto, Eiji*; Sawa, Kazuhiro; Kim, W. J.*; Jung, C. H.*; Park, J. Y.*
Nihon Kikai Gakkai Rombunshu, A, 76(764), p.383 - 385, 2010/04
no abstracts in English
Shibata, Taiju; Sumita, Junya; Makita, Taiyo*; Takagi, Takashi*; Kunimoto, Eiji; Sawa, Kazuhiro; Park, Y.*; Kim, W. J.*; Jung, C. H.*
no journal, ,
no abstracts in English
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