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Journal Articles

Observation of nuclear-spin Seebeck effect

Kikkawa, Takashi*; Reitz, D.*; Ito, Hiroaki*; Makiuchi, Takahiko*; Sugimoto, Takaaki*; Tsunekawa, Kakeru*; Daimon, Shunsuke*; Oyanagi, Koichi*; Ramos, R.*; Takahashi, Saburo*; et al.

Nature Communications (Internet), 12, p.4356_1 - 4356_7, 2021/07

 Times Cited Count:19 Percentile:88.38(Multidisciplinary Sciences)

Journal Articles

Cabling technology of Nb$$_3$$Sn conductor for ITER central solenoid

Takahashi, Yoshikazu; Nabara, Yoshihiro; Ozeki, Hidemasa; Hemmi, Tsutomu; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; Kawano, Katsumi; Oshikiri, Masayuki; Uno, Yasuhiro; et al.

IEEE Transactions on Applied Superconductivity, 24(3), p.4802404_1 - 4802404_4, 2014/06

 Times Cited Count:25 Percentile:72.88(Engineering, Electrical & Electronic)

Japan Atomic Energy Agency (JAEA) is procuring all amounts of Nb$$_3$$Sn conductors for Central Solenoid (CS) in the ITER project. Before start of mass-productions, the conductor should be tested to confirm superconducting performance in the SULTAN facility, Switzerland. The original design of cabling twist pitches is 45-85-145-250-450 mm, called normal twist pitch (NTP). The test results of the conductors with NTP was that current shearing temperature (Tcs) is decreasing due to electro-magnetic (EM) load cycles. On the other hand, the results of the conductors with short twist pitches (STP) of 25-45-80-150-450 mm show that the Tcs is stabilized during EM load cyclic tests. Because the conductors with STP have smaller void fraction, higher compaction ratio during cabling is required and possibility of damage on strands increases. The technology for the cables with STP was developed in Japanese cabling suppliers. The several key technologies will be described in this paper.

Journal Articles

Technology development for the construction of the ITER superconducting magnet system

Okuno, Kiyoshi; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Kawano, Katsumi; Koizumi, Norikiyo; Hamada, Kazuya; Nunoya, Yoshihiko; Matsui, Kunihiro; Nabara, Yoshihiro; et al.

Nuclear Fusion, 47(5), p.456 - 462, 2007/05

 Times Cited Count:8 Percentile:29.31(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Technology development for the construction of ITER superconducting magnet system

Okuno, Kiyoshi; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Kawano, Katsumi; Koizumi, Norikiyo; Hamada, Kazuya; Nunoya, Yoshihiko; Nabara, Yoshihiro; Kitamura, Kazunori; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

The ITER superconducting magnet system consists of 18 TF coils, one CS and six Poloidal Field (PF) coils. Among six PTs, Japan, EU and US will be responsible for major part of the superconducting magnets, and Japanese contribution will be the largest, including the following four areas: part of TF conductors, about half (9 out of 19) of TF coil winding packs, most of TF coil structures and part of CS conductor. Since 2004, Japan Atomic Energy Agency (JAEA) started preparation activities for procurement, including manufacturing studies to identify detailed fabrication processes and tools for critical components, such as TF coil winding and case, and manufacturing demonstrations at full scale level on Nb$$_{3}$$Sn strands and conductors and cryogenic structural materials, such as coil case segments and radial plates. Details are described in the following sections.

Journal Articles

Japanese contributions to the procurement of the ITER superconducting magnet

Okuno, Kiyoshi; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki

Fusion Engineering and Design, 81(20-22), p.2341 - 2349, 2006/11

 Times Cited Count:2 Percentile:17.18(Nuclear Science & Technology)

Japan is expected to make a major contribution to the procurement of the ITER superconducting magnet system. The ITER magnet system consists of 18 TF coils, one CS with six modules and six PF coils. The TF coils and CS have major features in unprecedented size of the magnets and structures and operations at 11 to 13 T high fields that require Nb$$_{3}$$Sn superconductor. Because of these features, significant efforts were made towards developing superconducting magnet technology to a level that will allow the ITER magnets to be built with confidence. The construction and testing of the CS and TF model coils have therefore been performed during the ITER Engineering Design Activity (EDA), and all ITER RD goals have been achieved. Based on these achievements, further development activities are now being performed at JAERI in tight collaboration with industry for the preparation of the ITER construction. The activities include analytic studies on design improvement and optimization, manufacturing studies to identify the detailed fabrication processes and tools, and manufacturing demonstrations on full-scale structural components (several tens of tons) such as made of new cryogenic materials, JJ1 and strengthened 316LN. Results from these activities will provide firm technical basis to achieve required performance of the magnets while maintaining both project schedule and cost and to reduce technical risks that may happen during the manufacturing phase.

Journal Articles

Development and test results of a 60kA HTS current lead for fusion application

Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Abe, Kanako*; Nunoya, Yoshihiko; Sugimoto, Makoto; Ando, Toshinari*; Okuno, Kiyoshi; Bono, Takaaki*; Tomioka, Akira*; et al.

Teion Kogaku, 39(3), p.122 - 129, 2004/03

JAERI has been developing a large-capacity high-temperature superconductor (HTS) current lead for fusion application, and succeeded in fabricating and testing a 60kA HTS current lead satisfying ITER requirements. Targets of performance are 1/10 heat leak and 1/3 electric power consumption of cryogenic system compared with a conventional lead. To achieve the target, selection of sheath material of HTS, optimizing the Cu part, reduction of joule heat at joint between HTS and Cu parts, improve of heat transfer between HTS and stainless steel tube. Developed 60kA HTS current lead satisfied the design condition and almost achieved the targets. Adoption of the HTS current lead can reduce 13% electric power consumption of cryogenic system for ITER.

Journal Articles

Quench analysis of an ITER 13T-40kA Nb$$_{3}$$Sn coil (CS insert)

Inaguchi, Takashi*; Hasegawa, Mitsuru*; Koizumi, Norikiyo; Isono, Takaaki; Hamada, Kazuya; Sugimoto, Makoto; Takahashi, Yoshikazu

Cryogenics, 44(2), p.121 - 130, 2004/02

 Times Cited Count:6 Percentile:27.83(Thermodynamics)

In order to analyze the quench characteristic of a cable-in-conduit (CIC) conductor that has a sub-cooling channel at the center of conductor cross section, an axisymmetrical two-dimensional calculation model was developed. The test and calculation results of the CS insert were compared regarding the pressure drop and the behavior of the total voltage, temperature and normal zone propagation in the quench. They show good agreement. Therefore, the effectiveness of the calculation model is verified. It was also found that there is coolant convection between the central channel and bundle region even in a steady state. This makes the pressure drop in the central channel larger than that in a cylindrical pipe which has a smooth surface. In addition, it was found that the higher temperature of the coolant flowing through the central channel heats the coolant and the cable in the bundle region. It can be said that the hot coolant flowing through the central channel accelerates normal zone propagation.

JAEA Reports

Analysis program for magnetic field, inductance of air-core coils; COIL

Yoshida, Kiyoshi; Isono, Takaaki; Sugimoto, Makoto; Okuno, Kiyoshi

JAERI-Data/Code 2003-014, 38 Pages, 2003/08

JAERI-Data-Code-2003-014.pdf:2.71MB

In case of designing a superconducting coil (SC), one must calculate a magnetic field (B) and its inductance (L) many times in order to arrange proper design parameters of SC because there are many design parameters to evaluate. SC cannot be designed by the optimum condition if a B and L can't be computed easily. When SC is energized, measurement values of B and L are very well agreed with calculated values. The B and L of the coil that doesn't contain a ferromagnetic material can be calculated by the numerical integration. The analytic method were developed and established in 1970's. This paper shows the calculation program COIL that has been developed by applying this analytic method in JAERI. COIL is qualified by the comparison between measured and calculated values in case of several real SC. COIL is specified to analyze SC of tokamak device. Even for a complicated tokamak device, B and L can be calculated in several minutes by the high performance of the recent personal computer. COIL contributes to design SC for ITER and others.

Journal Articles

Evaluation method of critical current and current sharing temperature for large-current Cable-in-Conduit conductors

Nunoya, Yoshihiko; Isono, Takaaki; Sugimoto, Makoto; Takahashi, Yoshikazu; Nishijima, Gen*; Matsui, Kunihiro; Koizumi, Norikiyo; Ando, Toshinari*; Okuno, Kiyoshi

IEEE Transactions on Applied Superconductivity, 13(2), p.1404 - 1407, 2003/06

 Times Cited Count:10 Percentile:49.37(Engineering, Electrical & Electronic)

Analysis of critical current ($$I_c$$) and current sharing temperature ($$T_{cs}$$) was performed to the ITER Center Solenoid (ITER-CS) Model Coil Insert. Voltage behavior related to normal state transition of the conductor during $$I_c$$ or $$T_{cs}$$ measurement has not been well understood especially in case of such a large cable with more than one thousand strands as this coil. From the detailed analysis of the voltage behavior of the coil, it is found that the average of electric field in the strand-longitudinal direction over the conductor cross section is equal to the average field of one strand along the conductor length, whose integral was measured by the voltage taps during the coil test. It is because twist pitch of the cable is less than the range of longitudinal field variation in this case. This evaluation method can estimate voltage behavior and predict $$I_c$$ and $$T_{cs}$$ values, which are important parameters for the design of a large conductor coil, based on the property of strands composing the conductor.

JAEA Reports

Nb$$_3$$Al insert experiment log book; 3rd Experiment of CS model coil

Sugimoto, Makoto; Koizumi, Norikiyo; Isono, Takaaki; Matsui, Kunihiro; Nunoya, Yoshihiko; Tsutsumi, Fumiaki*; Oshikiri, Masayuki*; Wakabayashi, Hiroshi*; Okuno, Kiyoshi; Tsuji, Hiroshi

JAERI-Tech 2002-080, 100 Pages, 2002/11

JAERI-Tech-2002-080.pdf:7.89MB

The cool down of CS model coil and Nb$$_3$$Al insert was started on March 4, 2002. It took almost one month and immediately started coil charge since April 3, 2002. The charge test of Nb$$_3$$Al insert and CS model coil was completed on May 2, 2002. All of the experiments including the warm up was also completed on May 30, 2002.In this campaign, total shot numbers were 102 and the size of the data file in the DAS (Data Acquisition System) was about 5.2 GB. This report is a database that consists of the log list and the log sheets of every shot.

Journal Articles

Quench characteristics and AC loss measurement in the ITER TF insert

Isono, Takaaki; Koizumi, Norikiyo; Matsui, Kunihiro; Sugimoto, Makoto; Hamada, Kazuya; Nunoya, Yoshihiko; Rodin, I.*; CS Model Coil Test Group

Teion Kogaku, 37(10), p.539 - 544, 2002/10

The Toroidal Field (TF) insert has been developed by Russia to demonstrate the TF conductor performance and tested in the bore of the Central Solenoid (CS) model coil, which applies a 13-T magnetic field. In this paper, quench property and AC loss measurement is described. Major difference between TF and CS conductor is the jacket shape and existence of mandrel and they effect on quench property and AC loss measurement. Quench test was performed at 46kA, 12T, 6.5K and the currents of the TF insert and the CS model coil were kept for 9 seconds after normal zone appearance. An inductive heater of 200mm length made a quench. Normal zone length was 16m, and the maximum velocity was 2m/s. Maximum temperature is estimated to be 160 K with some errors. Hysteresis loss was measured by calorimetric method and the values are almost same as the expected values from strand data. It was pointed out that coupling loss measurement using calorimetric method is difficult because loss at the mandrel is more than 10 times higher than coupling loss.

Journal Articles

Current sharing temperature of the ITER-TF insert

Nunoya, Yoshihiko; Sugimoto, Makoto; Isono, Takaaki; Hamada, Kazuya; Matsui, Kunihiro; Okuno, Kiyoshi; CS Model Coil Test Group

Teion Kogaku, 37(10), p.523 - 530, 2002/10

Vurrent sharing temperature (Tcs) measurement of ITER toroidal field insert was performed. The coil is Nb$$_3$$Sn superconducting coil and was installed inside of the ITER CS model coil as a backup field coil. Relation between the voltage of individual strand composing TF insert conductor and the measured voltage using the taps on the jacket is investigated and the evaluation method for Tcs measurement was established. The obtained results shows that there was discrepancy between the expected value from the strand data and the measured value which is lower by about 1.2K. Some discrepancy was already observed just after cool down of the insert before energizing.

JAEA Reports

TF insert experiment log book; 2nd experiment of CS model coil

Sugimoto, Makoto; Isono, Takaaki; Matsui, Kunihiro; Nunoya, Yoshihiko; Tsutsumi, Fumiaki*; Tamiya, Tadatoshi*; Oshikiri, Masayuki*; Wakabayashi, Hiroshi*; Okuno, Kiyoshi; Tsuji, Hiroshi

JAERI-Tech 2001-085, 104 Pages, 2001/12

JAERI-Tech-2001-085.pdf:4.64MB

no abstracts in English

Journal Articles

Development of ITER-CS model coil terminal assembling by using indium wires

Takahashi, Yoshikazu; Kato, Takashi; Nunoya, Yoshihiko; Ando, Toshinari; Nishijima, Gen; Nakajima, Hideo; Hiyama, Tadao; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; et al.

Fusion Engineering and Design, 58-59, p.93 - 97, 2001/11

 Times Cited Count:10 Percentile:59.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of critial current performance of 13 T-46 kA steel-jacketed Nb$$_{3}$$Al conductor

Koizumi, Norikiyo; Azuma, Katsunori*; Tsuchiya, Yoshinori; Matsui, Kunihiro; Takahashi, Yoshikazu; Nakajima, Hideo; Nishijima, Gen; Nunoya, Yoshihiko; Ando, Toshinari; Isono, Takaaki; et al.

Fusion Engineering and Design, 58-59, p.1 - 5, 2001/11

 Times Cited Count:2 Percentile:19.66(Nuclear Science & Technology)

no abstracts in English

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:74.85(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Pulse operation test of the ITER central solenoid model coil using the JT-60 power supply

Terakado, Tsunehisa; Okano, Jun; Shimada, Katsuhiro; Miura, Yushi; Yamashita, Yoshiki*; Matsukawa, Makoto; Hosogane, Nobuyuki; Tsuji, Hiroshi; Ando, Toshinari*; Takahashi, Yoshikazu; et al.

JAERI-Tech 2001-056, 24 Pages, 2001/08

JAERI-Tech-2001-056.pdf:1.17MB

no abstracts in English

Journal Articles

Evaluation of critical current performance of a Nb$$_{3}$$Al conductor with stainless steel conduit

Koizumi, Norikiyo; Takahashi, Yoshikazu; Nakajima, Hideo; Tsuchiya, Yoshinori; Matsui, Kunihiro; Nunoya, Yoshihiko; Ando, Toshinari; Hiyama, Tadao; Kato, Takashi; Isono, Takaaki; et al.

Teion Kogaku, 36(8), p.478 - 485, 2001/08

no abstracts in English

Journal Articles

CS model coil test facility

Kato, Takashi; Nakajima, Hideo; Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Sugimoto, Makoto; Nunoya, Yoshihiko; Koizumi, Norikiyo; Matsui, Kunihiro; Oshikiri, Masayuki*; et al.

Teion Kogaku, 36(6), p.315 - 323, 2001/06

no abstracts in English

Journal Articles

Critical current and sharing temperature of the ITER-CS insert coil

Nunoya, Yoshihiko; Isono, Takaaki; Sugimoto, Makoto; Takahashi, Yoshikazu; Ando, Toshinari; Nishijima, Gen; CS Model Coil Test Group

Teion Kogaku, 36(6), p.354 - 360, 2001/06

no abstracts in English

61 (Records 1-20 displayed on this page)