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Koide, Yoshihiko; Yoshida, Kiyoshi; Wanner, M.*; Barabaschi, P.*; Cucchiaro, A.*; Davis, S.*; Decool, P.*; Di Pietro, E.*; Disset, G.*; Genini, L.*; et al.
Nuclear Fusion, 55(8), p.086001_1 - 086001_7, 2015/08
Times Cited Count：31 Percentile：83.35(Physics, Fluids & Plasmas)The most distinctive feature of the superconducting magnet system for JT-60SA is the optimized coil structure in terms of the space utilization as well as the highly accurate coil manufacturing, thus meeting the requirements for the steady-state tokamak research: A conceptually new outer inter-coil structure separated from the casing is introduced to the toroidal field coils to realize their slender shape, allowing large-bore diagnostic ports for detailed plasma measurements. A method to minimize the manufacturing error of the equilibrium-field coils has been established, aiming at the precise plasma shape/position control. A compact butt-joint has been successfully developed for the Central Solenoid, which allows an optimized utilization of the limited space for the Central Solenoid to extend the duration of the plasma pulse.
Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kashiwa, Yoshitoshi; Yoshizawa, Norio; Yoshida, Kiyoshi; Hasegawa, Mitsuru*; Kuno, Kazuo*; Nomoto, Kazuhiro*; Horii, Hiroyuki*
Fusion Engineering and Design, 88(6-8), p.551 - 554, 2013/10
Times Cited Count：8 Percentile：53.52(Nuclear Science & Technology)The programme of constructing JT-60SA device is progressing under the framework of the Broader Approach project. Superconducting poloidal field (PF) coil system, which was decided to be procured by Japan, consists of a central solenoid (CS) with four solenoid modules and six equilibrium field (EF) coils. Each of EF coil has individual diameters, 4.5 to 12 m. Fabrication of EF4 coil, which is set at the lowermost of torus, was started from the beginning of 2009 as a first EF coil. EF4 coil has ten double pancake (DP) coils, and sizes of circularity were measured for all DP coil after curing process. Maximum error of circularity was 3.1 mm, which was nearly a half of the design tolerance, 6 mm. After stacking these DP coils, winding pack of EF4 was completed in the spring of 2012. After optimizing the positions of DP coils to cancel the error of circulation which each DP coil has, error of radial current centre of DP coils will be achieved in the range between + 0.2 to - 0.4 mm. Structural analysis of terminal structure was also performed. Terminal part has a pair of conductors bended toward the lower side of winding pack. A side of them (positive terminal) was covered by stainless steel armor to prevent the movement by electromagnetic force because a length of conductor was longer due to starting from the top of winding pack. Another side (negative terminal) was not covered by armor in the first design because this length was relatively short. However, it was clear on the structural analysis that mechanical strength of insulation around this terminal was not sufficient. Therefore, we also reinforced this side with stainless steel. From this April, fabrication of EF coils with large bore (larger than 8 m of diameter) will be started at the facility built in JAEA Naka site. In this paper, we will discuss about technological problem during the fabrication of large bore EF coils, such as temperature control at the winding process.
Kizu, Kaname; Kashiwa, Yoshitoshi; Murakami, Haruyuki; Obana, Tetsuhiro*; Takahata, Kazuya*; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Hamaguchi, Shinji*; Matsui, Kunihiro; Nakamura, Kazuya*; et al.
Fusion Engineering and Design, 86(6-8), p.1432 - 1435, 2011/10
Times Cited Count：8 Percentile：53.37(Nuclear Science & Technology)In JT-60SA, central solenoid (CS) and plasma equilibrium field (EF) coils are procured by Japan. EF coil conductors are NbTi cable-in-conduit (CIC) conductor. Delivered superconducting cables and jackets are fabricated into CIC conductors at the jacketing facility with the length of 680 m constructed in the Naka site of JAEA. The production of superconductors with 444 m in length for actual EF coils was started from March 2010. The measurements of superconducting performance like current sharing temperature (Tcs) were conducted prior to the mass production. The measured Tcs was agreed with the expectation values from strand values indicating that no degradation was happened by production process.
Kizu, Kaname; Tsuchiya, Katsuhiko; Kashiwa, Yoshitoshi; Murakami, Haruyuki; Yoshida, Kiyoshi
IEEE Transactions on Applied Superconductivity, 20(3), p.538 - 541, 2010/06
Times Cited Count：9 Percentile：48.56(Engineering, Electrical & Electronic)The CS and EF coils in JT-60SA are procured by Japan. The conductor for CS is Nb
Sn cable-in-conduit (CIC). On the other hand, EF coil conductors are NbTi CIC conductor. Delivered superconducting cables and jackets are fabricated into CIC conductors at the jacketing facility constructed in the Naka site of JAEA. The length of jacketing facility is about 660 m. The production of superconducting cables and jackets were started from April 2008. Since the superconducting cables and jackets following the specifications were produced well, the mass production was started. In this paper, the design of jacketing line and the first production results of CIC conductor will be described.
Higashijima, Satoru; Sakurai, Shinji; Suzuki, Satoshi; Yokoyama, Kenji; Kashiwa, Yoshitoshi; Masaki, Kei; Shibama, Yusuke; Takechi, Manabu; Shibanuma, Kiyoshi; Sakasai, Akira; et al.
Fusion Engineering and Design, 84(2-6), p.949 - 952, 2009/06
Times Cited Count：9 Percentile：53.3(Nuclear Science & Technology)An upgrading device of JT-60 tokamak with fully superconducting coils (JT-60SA) is constructed under both the Japanese domestic program and the international program "Broader Approach". The maximum heat flux to JT-60SA divertor is estimated to 15 MW/m
for 100 s, and a monoblock-type CFC divertor armor is promising. The JT-60SA armor consists of CFC monoblocks, a cooling CuCrZr screw-tube, and a thin OFHC-Cu buffer layer, and the brazed joints are essential for the armor. Metalization inside CFC monoblock is applied for further improvement, and we confirmed again that the mock-up has heat removal capability in excess of ITER requirement. For optimization of the fabrication method and understanding of the production yield, the mock-ups corresponding to quantity produced in one furnace is also produced, and the half of the mock-ups could remove 15 MW/m as required. This summarizes the recent progress of design and mock-up test results for JT-60SA divertor armor.
Fukumoto, Naoyuki*; Ogawa, Hiroaki; Nagata, Masayoshi*; Uyama, Tadao*; Shibata, Takatoshi; Kashiwa, Yoshitoshi; Suzuki, Sadaaki; Kusama, Yoshinori; JFT-2M Group
Fusion Engineering and Design, 81(23-24), p.2849 - 2857, 2006/11
Times Cited Count：7 Percentile：46.04(Nuclear Science & Technology)no abstracts in English
Ogawa, Hiroaki; Ogawa, Toshihide; Tsuzuki, Kazuhiro; Kawashima, Hisato; Kasai, Satoshi*; Kashiwa, Yoshitoshi; Hasegawa, Koichi; Suzuki, Sadaaki; Shibata, Takatoshi; Miura, Yukitoshi; et al.
Fusion Science and Technology, 49(2), p.209 - 224, 2006/02
Times Cited Count：3 Percentile：24.11(Nuclear Science & Technology)no abstracts in English
Ogawa, Toshihide; Ogawa, Hiroaki; Miura, Yukitoshi; Niimi, Hironobu*; Kimura, Haruyuki; Kashiwa, Yoshitoshi; Shibata, Takatoshi; Yamamoto, Masahiro; Fukumoto, Naoyuki*; Nagata, Masayoshi*; et al.
Journal of Nuclear Materials, 290-293, p.454 - 458, 2001/03
Times Cited Count：7 Percentile：48.68(Materials Science, Multidisciplinary)no abstracts in English
Miura, Yukitoshi; *; *; Hoshino, Katsumichi; *; *; Kasai, Satoshi; Kawakami, Tomohide; Kawashima, Hisato; Maeda, M.*; et al.
Fusion Energy 1996, p.167 - 175, 1997/05
no abstracts in English
*; *; *; *; *; *; *; Oikawa, Toshihiro; *; *; et al.
Fusion Energy 1996, p.885 - 890, 1997/05
no abstracts in English
Kashiwa, Yoshitoshi; Okano, Fuminori; ;
IPPJ-DT-140, p.186 - 186, 1988/00
no abstracts in English
Matsuda, Toshiaki; Matoba, Toru; Mori, Masahiro; Kawakami, Tomohide; Kashiwa, Yoshitoshi; ; Matsuzaki, Yoshimi; *
Nihon Genshiryoku Gakkai-Shi, 30(1), p.49 - 63, 1988/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
Okano, Fuminori; Matsuzaki, Yoshimi; Kashiwa, Yoshitoshi; *
Shinku, 31(5), p.413 - 415, 1988/00
no abstracts in English
Matsuda, Toshiaki; Matoba, Toru; Mori, Masahiro; Kawakami, Tomohide; Kashiwa, Yoshitoshi; ; Matsuzaki, Yoshimi; *
JAERI-M 87-129, 44 Pages, 1987/08
no abstracts in English
Higashijima, Satoru; Sakurai, Shinji; Kashiwa, Yoshitoshi; Masaki, Kei; Shibama, Yusuke; Sakasai, Akira; Matsukawa, Makoto
no journal, ,
no abstracts in English
Kizu, Kaname; Tsuchiya, Katsuhiko; Kashiwa, Yoshitoshi; Murakami, Haruyuki; Yoshida, Kiyoshi
no journal, ,
In JT-60SA, magnets system consists of 18 toroidal field coils, 4 stacks of central solenoid (CS) and 6 plasma equilibrium field (EF) coils. The maximum magnetic field and current of CS and EF coils is 9 T, 20 kA and 6.2 T, 20 kA, respectively. The conductor for CS is NbSn cable-in-conduit conductor. On the other hand, EF coil conductors are NbTi conductor. Delivered superconducting cables and jackets are fabricated into conductors at the jacketing facility constructed in the Naka site of JAEA. The length of jacketing facility is about 660 m. The production of superconducting cables and jackets were started from April 2008. Since the superconducting strands and copper dummy cables following the specifications were produced well, the mass production of strands was started. The first superconducting cable will be delivered to Naka site in April 2009. In this paper, the design of jacketing line and the first production results of conductor will be described.
Kizu, Kaname; Kashiwa, Yoshitoshi; Murakami, Haruyuki; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Yanagi, Nagato*; Imagawa, Shinsaku*; et al.
no journal, ,
In JT-60SA, magnets system consists of 18 toroidal field (TF) coils, 4 stacks of central solenoid (CS) and 6 plasma equilibrium field (EF) coils. The CS and EF coils are procured by Japan. The maximum magnetic field and maximum current of EF coils is 6.2 T, 20 kA. EF coil conductors are NbTi cable-in-conduit (CIC) conductor. Delivered superconducting cables and jackets are fabricated into CIC conductors at the jacketing facility with the length of 680 m constructed in the Naka site of JAEA. The production of superconductors with 444 m in length for actual EF coils was started from March 2010. The measurements of superconducting performance like current sharing temperature were conducted prior to the mass production. The production and test results of EF conductors will be described.
Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji; Kashiwa, Yoshitoshi; Honda, Atsushi; Yoshida, Kiyoshi
no journal, ,
no abstracts in English
Kashiwa, Yoshitoshi; Kizu, Kaname; Yoshida, Kiyoshi
no journal, ,
no abstracts in English
Kizu, Kaname; Tsuchiya, Katsuhiko; Kashiwa, Yoshitoshi; Murakami, Haruyuki; Ichige, Toshikatsu; Asakawa, Shuji; Yoshida, Kiyoshi
no journal, ,
Superconducting cables and jackets delivered from manufacturer are fabricated into superconductor at jacketing facility in Japan Atomic Energy Agency. Then, conductors are supplied to coil manufacturer. Fabrication of conductors for equilibrium field coils were started from 2010. 26 conductors were fabricated up to 9 September 2011. 22 conductors at storage building were loosened by Great East Japan Earthquake. Conductors were repaired. It was confirmed that conductors can be used for coil. On the other hand, fabrication of conductors for central solenoid was started from July 2011. 4 conductors were fabricated.
