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Oral presentation

Detailed manufacturing design and large-scale trial manufactures of ITER TF coil structures

Nakajima, Hideo; Niimi, Kenichiro; Omori, Junji; Takano, Katsutoshi; Hamada, Kazuya; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Qualification of structural materials for ITER TF coil

Nakajima, Hideo; Takano, Katsutoshi; Tsutsumi, Fumiaki; Kawano, Katsumi; Hamada, Kazuya; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Codes for fusion facilities; Rules on superconducting magnet structure; JSME S KA1-2008

Nishimura, Arata*; Nakajima, Hideo

no journal, , 

no abstracts in English

Oral presentation

Analysis of current distribution in joint of conductor sample for ITER Central Solenoid (CS)

Hase, Takashi*; Shimizu, Tatsuya; Hemmi, Tsutomu; Matsui, Kunihiro; Koizumi, Norikiyo; Takahashi, Yoshikazu; Okuno, Kiyoshi

no journal, , 

Nb$$_{3}$$Sn conductors (40 kA, 13 T) are employed in ITER CS. The characteristics of the sample in which two kinds of conductors are connected with OFC blocks will be evaluated. The joint part will be exposed to fields widely ranging from 0.29-8.4 T when an external field of 11 T is generated. Therefore, current distribution due to the magnetic resistance may bring incorrect evaluation of performance of the sample. The current distribution in the joint part of the conductor has been analyzed with the FEM to confirm the speculation and to get an idea for make the current distribution more uniformly. It has been found as a result that the current distribution in the conventional joint structure employing the OFC with a RRR of 100 leads to a current density ratio of 1.65, though a total resistance is very low. On the contrary, by employing copper plate of RRR = 4, the current density ratio can be reduced to 1.23, while keeping the total resistance below 2 n$$Omega$$.

Oral presentation

Development of manufacturing technology of radial plate and cover plate

Takano, Katsutoshi; Nakajima, Hideo; Koizumi, Norikiyo; Hamada, Kazuya; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Engineering materials diffractometer "TAKUMI" and stress/strain effects on industrial superconducting composites

Harjo, S.; Aizawa, Kazuya; Ito, Takayoshi; Osamura, Kozo*; Awaji, Satoshi*; Hemmi, Tsutomu; Machiya, Shutaro*; Tsuchiya, Yoshinori*; Matsui, Kunihiro; Nishijima, Gen*

no journal, , 

no abstracts in English

Oral presentation

Detailed manufacturing design and large-scale trial manufactures of ITER TF coil winding pack

Koizumi, Norikiyo; Nakajima, Hideo; Matsui, Kunihiro; Takano, Katsutoshi; Hemmi, Tsutomu; Omori, Junji; Shimizu, Tatsuya; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Progress in procurement for ITER superconductors

Takahashi, Yoshikazu; Isono, Takaaki; Hamada, Kazuya; Nunoya, Yoshihiko; Nabara, Yoshihiro; Matsui, Kunihiro; Hemmi, Tsutomu; Koizumi, Norikiyo; Nakajima, Hideo; Kawano, Katsumi; et al.

no journal, , 

The toroidal field (TF) coil system of the International Thermonuclear Experimental Reactor (ITER) consists of 18 D-shape coils. The operating current, the maximum field and the stored magnetic energy are 68 kA, 11.8 T and about 41 GJ, respectively. Nb$$_{3}$$Sn cable-in-conduit conductor with a central channel is used. The superconducting cable consists of 900 Nb$$_{3}$$Sn strands and 522 copper strands, and they are cabled to a 5th stage cable with a central cooling spiral. The conductor manufacture started in 4 companies (strands in 2 companies, cabling, jacketing) in Japan, from March 2008. The first batches of the strands were successfully completed in 2 companies. These strands satisfy their specifications. The performance of these strands will be mainly reported.

Oral presentation

Support structure design for the poloidal field coil system in JT-60SA

Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Asakawa, Shuji; Kuramochi, Masaya; Yoshida, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Quench test for NbTi CIC conductor of JT-60SA equilibrium field coil

Murakami, Haruyuki; Ichige, Toshikatsu; Kizu, Kaname; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Hamaguchi, Shinji*; Takahata, Kazuya*; Imagawa, Shinsaku*; Mito, Toshiyuki*

no journal, , 

no abstracts in English

Oral presentation

Numerical simulation on critical current degradation of Nb$$_{3}$$Sn strand with different cross sectional structure in CICC

Kajitani, Hideki*; Ueda, Hiroshi*; Ishiyama, Atsushi*; Murakami, Haruyuki; Koizumi, Norikiyo; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Construction of the jacketing facility and first production results of superconductor for JT-60SA

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 Nb$$_{3}$$Sn 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.

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