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Journal Articles

Effect of change of aging heat treatment pattern on the JK2LB jacket for the ITER central solenoid

Ozeki, Hidemasa; Saito, Toru; Kawano, Katsumi; Takahashi, Yoshikazu; Nunoya, Yoshihiko; Yamazaki, Toru; Isono, Takaaki

Physics Procedia, 67, p.1010 - 1015, 2015/07

 Times Cited Count:3 Percentile:72.21(Physics, Applied)

Journal Articles

Mechanical properties of high manganese austenitic stainless steel JK2LB for ITER central solenoid jacket material

Saito, Toru; Kawano, Katsumi; Yamazaki, Toru; Ozeki, Hidemasa; Isono, Takaaki; Hamada, Kazuya*; Devred, A.*; Vostner, A.*

Physics Procedia, 67, p.1016 - 1021, 2015/07

 Times Cited Count:6 Percentile:86.55(Physics, Applied)

Journal Articles

Non-destructive examination of jacket sections for ITER central solenoid conductors

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

IEEE Transactions on Applied Superconductivity, 25(3), p.4200904_1 - 4200904_4, 2015/06

 Times Cited Count:4 Percentile:24.66(Engineering, Electrical & Electronic)

The Japan Atomic Energy Agency (JAEA) is responsible for procuring all amounts of Central Solenoid (CS) Conductors for ITER, including CS jacket sections. The conductor is cable-in-conduit conductor (CICC) with a central spiral. A total of 576 Nb$$_{3}$$Sn strands and 288 copper strands are cabled around the central spiral. The maximum operating current is 40 kA at magnetic field of 13 T. CS jacket section is circular in square type tube made of JK2LB, which is high manganese stainless steel with boron added. Unit length of jacket sections is 7 m and 6,300 sections will be manufactured and inspected. Outer/inner dimension and weight are 51.3/35.3 mm and around 90 kg, respectively. Eddy Current Test (ECT) and Phased Array Ultrasonic Test (PAUT) were developed for non-destructive examination. The defects on inner and outer surfaces can be detected by ECT. The defects inside jacket section can be detected by PAUT. These technology and the inspected results are reported in this paper.

Journal Articles

Behavior of Nb$$_{3}$$Sn cable assembled with conduit for ITER central solenoid

Nabara, Yoshihiro; Suwa, Tomone; Takahashi, Yoshikazu; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Sakurai, Takeru; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4200305_1 - 4200305_5, 2015/06

 Times Cited Count:0 Percentile:0.00(Engineering, Electrical & Electronic)

Journal Articles

Fabrication process qualification of TF Insert Coil using real ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4200804_1 - 4200804_4, 2015/06

 Times Cited Count:0 Percentile:0.00(Engineering, Electrical & Electronic)

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:26 Percentile:73.98(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

Establishment of production process of JK2LB jacket section for ITER CS

Ozeki, Hidemasa; Hamada, Kazuya; Takahashi, Yoshikazu; Nunoya, Yoshihiko; Kawano, Katsumi; Oshikiri, Masayuki; Saito, Toru; Teshima, Osamu*; Matsunami, Masahiro*

IEEE Transactions on Applied Superconductivity, 24(3), p.4800604_1 - 4800604_4, 2014/06

 Times Cited Count:16 Percentile:61.18(Engineering, Electrical & Electronic)

Journal Articles

Optimization of heat treatment of Japanese Nb$$_3$$Sn conductors for toroidal field coils in ITER

Nabara, Yoshihiro; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Suwa, Tomone; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; Koizumi, Norikiyo; et al.

IEEE Transactions on Applied Superconductivity, 24(3), p.6000605_1 - 6000605_5, 2014/06

 Times Cited Count:7 Percentile:38.76(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Examination of Nb$$_{3}$$Sn conductors for ITER central solenoids

Nabara, Yoshihiro; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; Takahashi, Yoshikazu; Matsui, Kunihiro; Koizumi, Norikiyo; et al.

IEEE Transactions on Applied Superconductivity, 23(3), p.4801604_1 - 4801604_4, 2013/06

 Times Cited Count:10 Percentile:47.28(Engineering, Electrical & Electronic)

no abstracts in English

Oral presentation

Development of Nb$$_{3}$$Sn cables for ITER central solenoid (CS) coil

Takahashi, Yoshikazu; Nabara, Yoshihiro; Ozeki, Hidemasa; Hemmi, Tsutomu; Nunoya, Yoshihiko; Isono, Takaaki; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Uno, Yasuhiro; Shibutani, Kazuyuki*; et al.

no journal, , 

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 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.

Oral presentation

Performance examination of Nb$$_3$$Sn superconductor for ITER CS coil

Nabara, Yoshihiro; Suwa, Tomone; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Sakurai, Takeru; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; et al.

no journal, , 

no abstracts in English

Oral presentation

Test results of CS insert for ITER; Test method

Isono, Takaaki; Kawano, Katsumi; Ozeki, Hidemasa; Saito, Toru; Nabara, Yoshihiro; Suwa, Tomone; Shimono, Mitsugu; Ebisawa, Noboru; Sato, Minoru; Uno, Yasuhiro; et al.

no journal, , 

JAEA is procuring conductors for ITER Central Solenoid (CS) and has evaluated its superconducting performance using CS Model Coil Test facility. We measured Tcs values during cyclic charge of 16,000 cycles and warm-up and cool-down cycle of 3 times. And we measured effect of coil deformation by electro-magnetic force on Tcs values and performed quench test. In this presentation, test method will be reported.

Oral presentation

Inductive heating test of ITER CS insert coil

Ozeki, Hidemasa; Suwa, Tomone; Isono, Takaaki; Takahashi, Yoshikazu; Kawano, Katsumi; Nabara, Yoshihiro; Saito, Toru; Nunoya, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Mechanical property of ITER Central Solenoid (CS) insert coil conductor

Saito, Toru; Ozeki, Hidemasa; Suwa, Tomone; Nabara, Yoshihiro; Kawano, Katsumi; Takahashi, Yoshikazu; Isono, Takaaki; Nunoya, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Preparation for procurement of ITER CS conductor jacket

Ozeki, Hidemasa; Hamada, Kazuya; Nunoya, Yoshihiko; Kawano, Katsumi; Takahashi, Yoshikazu; Oshikiri, Masayuki; Saito, Toru; Matsunami, Masahiro*; Teshima, Osamu*

no journal, , 

no abstracts in English

Oral presentation

Progress of procurement of ITER central solenoid jacket

Ozeki, Hidemasa; Hamada, Kazuya; Takahashi, Yoshikazu; Nunoya, Yoshihiko; Kawano, Katsumi; Oshikiri, Masayuki; Saito, Toru; Isono, Takaaki; Teshima, Osamu*; Matsunami, Masahiro*

no journal, , 

no abstracts in English

Oral presentation

Quench test on ITER Nb$$_{3}$$Sn CICC

Suwa, Tomone; Ozeki, Hidemasa; Nabara, Yoshihiro; Saito, Toru*; Kawano, Katsumi; Takahashi, Yoshikazu; Isono, Takaaki; Nunoya, Yoshihiko

no journal, , 

no abstracts in English

Oral presentation

Performance of superconductors for ITER central solenoids

Nabara, Yoshihiro; Hemmi, Tsutomu; Kajitani, Hideki; Ozeki, Hidemasa; Iguchi, Masahide; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; Koizumi, Norikiyo; Tsutsumi, Fumiaki; et al.

no journal, , 

no abstracts in English

Oral presentation

Development and production of cables for ITER

Takahashi, Yoshikazu; Nabara, Yoshihiro; Nunoya, Yoshihiko; Suwa, Tomone; Tsutsumi, Fumiaki; Oshikiri, Masayuki; Ozeki, Hidemasa; Shibutani, Kazuyuki*; Kawano, Katsumi; Kawasaki, Tsutomu*; et al.

no journal, , 

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 cable with a shorter twist pitch shows no degradation of Tcs against to electromagnetic load cycles. However, it is difficult to make the cable, because the diameter of the cable with shorter twist pitch is larger and the cable has to compact more. The technology for the cables with STP was developed in Japanese cabling suppliers. The several key technologies and production will be described in this paper.

Oral presentation

Non-destructive examination of jacket sections for ITER central solenoid (CS) coil

Takahashi, Yoshikazu; Suwa, Tomone; Nabara, Yoshihiro; Ozeki, Hidemasa; Nunoya, Yoshihiko; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Takamura, Jun; Shibutani, Kazuyuki*; Chuheishi, Shinji; et al.

no journal, , 

The Japan Atomic Energy Agency (JAEA) is responsible for procuring all amounts of Central Solenoid (CS) Conductors for ITER, including CS jacket sections. The conductor is cable-in-conduit conductor (CICC) with a central spiral. A total of 576 Nb$$_{3}$$Sn strands and 288 copper strands are cabled around the central spiral. The maximum operating current is 40 kA at magnetic field of 13 T. CS jacket section is circular in square type tube made of JK2LB, which is high manganese stainless steel with boron added. Unit length of jacket sections is 7 m and 6,300 sections will be manufactured and inspected. Outer/inner dimension and weight are 51.3/35.3 mm and around 90 kg, respectively. Eddy Current Test (ECT) and Phased Array Ultrasonic Test (PAUT) were developed for non-destructive examination. The defects on inner and outer surfaces can be detected by ECT. The defects inside jacket section can be detected by PAUT. These technology and the inspected results are reported in this paper.

25 (Records 1-20 displayed on this page)