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Journal Articles

Demonstration of JK2LB jacket fabrication for ITER central solenoid

Hamada, Kazuya; Nakajima, Hideo; Kawano, Katsumi; Takano, Katsutoshi*; Tsutsumi, Fumiaki*; Seki, Shuichi*; Okuno, Kiyoshi; Fujitsuna, Nobuyuki*; Mizoguchi, Mitsuru*

IEEE Transactions on Applied Superconductivity, 16(2), p.787 - 790, 2006/06

 Times Cited Count:6 Percentile:37.33(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

A New model to simulate critical current degradation of a large CICC by taking into account strand bending

Koizumi, Norikiyo; Nunoya, Yoshihiko; Okuno, Kiyoshi

IEEE Transactions on Applied Superconductivity, 16(2), p.831 - 834, 2006/06

 Times Cited Count:24 Percentile:70.73(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Numerical simulation of the critical current and n-value in Nb$$_{3}$$Sn strand subjected to bending strain

Hirohashi, Masayuki*; Murakami, Haruyuki*; Ishiyama, Atsushi*; Ueda, Hiroshi*; Koizumi, Norikiyo; Okuno, Kiyoshi

IEEE Transactions on Applied Superconductivity, 16(2), p.1721 - 1724, 2006/06

 Times Cited Count:9 Percentile:46.66(Engineering, Electrical & Electronic)

To demonstrate the applicability of Nb$$_{3}$$Sn CICCs to ITER, four Nb$$_{3}$$Sn model coils have been constructed and tested. The experimental results showed that the measured critical current (Ic) degraded. In addition, the larger is the applied electromagnetic force, the larger the magnitude of the degradation is. The degradation in n-value was also observed. One of the explanations of this degradation is a local strand bending. This consideration has been supported by the test results. However, general dependence of Ic on periodic bending strain has not been clarified in this test since the experiments were carried out at a certain magnetic field, temperature and strain. Therefore, a numerical simulation code was developed to study the general dependence of the Ic and n-value of the Nb$$_{3}$$Sn strand on periodic bending strain. A distributed constant circuit model is applied to simulate current transfer among the filaments in the strand. The simulation results show relatively good agreement with the experiment results but some modification in modeling is required for more accurate simulation.

Journal Articles

Nuclear technology and potential ripple effect of superconducting magnets for fusion power plant

Nishimura, Arata*; Muroga, Takeo*; Takeuchi, Takao*; Nishitani, Takeo; Morioka, Atsuhiko

Fusion Engineering and Design, 81(8-14), p.1675 - 1681, 2006/02

 Times Cited Count:3 Percentile:24.11(Nuclear Science & Technology)

In a fusion reactor plant, a neutral beam injector (NBI) will be operated for a long time, and it will allow neutron streaming from NBI ports to outside of the plasma vacuum vessel. It requires the superconducting magnet to develop nuclear technology to produce stable magnetic field and to reduce activation of the magnet components. In this report, the back ground of the necessity and the contents of the nuclear technology of the superconducting magnets for fusion application are discussed and some typical investigation results are presented, which are the neutron irradiation effect on Nb$$_{3}$$Sn wire, the development of low activation superconducting wire, and the design concept to reduce nuclear heating and nuclear transformation by streaming. In addition, recent activities in high energy particle physics are introduced and potential ripple effect of the technology of the superconducting magnets is described briefly.

Journal Articles

Development of advanced superconducting coil technologies for the National Centralized Tokamak

Kizu, Kaname; Miura, Yushi*; Tsuchiya, Katsuhiko; Ando, Toshinari*; Koizumi, Norikiyo; Matsui, Kunihiro*; Sakasai, Akira; Tamai, Hiroshi; Matsukawa, Makoto; Ishida, Shinichi; et al.

Nuclear Fusion, 45(11), p.1302 - 1308, 2005/11

 Times Cited Count:4 Percentile:14.24(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Experimental investigation on the effect of transverse electromagnetic force on the V-T curve of the CIC conductor

Nunoya, Yoshihiko; Isono, Takaaki; Okuno, Kiyoshi

IEEE Transactions on Applied Superconductivity, 14(2), p.1468 - 1472, 2004/06

 Times Cited Count:45 Percentile:83.44(Engineering, Electrical & Electronic)

The voltage temperature characteristic curve (V-T curve) observed in the large-current Nb$$_{3}$$Sn CIC conductor, which was used in the ITER CS Insert, showed a gradual take-off toward normal state as compared with the V-T curve of an individual strand composing the conductor. The gradual take-off corresponds to the reduction in so-called "n-value." In addition, the take-off shifted to lower temperature than that of the strand, namely lower current sharing temperature (Tcs) or lower critical current (Ic). These behaviors cannot be explained by non-uniform magnetic field accompanying enlargement of the conductor, or by non-uniform contact resistance of the conductor terminals. Investigation is therefore required to clarify the condition of each strand in such large CIC conductor, especially in terms of the strain state under large electromagnetic force. In a CIC conductor, since strands are twisted to form a cable, each strand is mechanically supported by a nearby strand at an interval related to the twist pitch. Between two supporting points, the strand is fee to move under transverse force and a cyclic deformation will occur along the strand length. We designed the apparatus to simulate this cyclic deformation and measured the V-T characteristic of the strand. When the strand received the transverse force of about 500 N/m, n-value reduced to one-fifth (about 6) of the original value, which corresponds to that observed in the CS Insert. The level of the force agreed to the electromagnetic force when the CS Insert was energized to 46 kA at 13 T (about 40 A each strand $$times$$ 13 T = 520 N/m). This suggests that the transverse force acting on each strand can explain the behavior of the V-T curve of the large-current CIC conductor.

Journal Articles

Performance of joints in the CS model coil and application to the full size ITER coils

Takahashi, Yoshikazu; Yoshida, Kiyoshi; Mitchell, N.*; Bessette, D.*; Nunoya, Yoshihiko; Matsui, Kunihiro; Koizumi, Norikiyo; Isono, Takaaki; Okuno, Kiyoshi

IEEE Transactions on Applied Superconductivity, 14(2), p.1410 - 1413, 2004/06

 Times Cited Count:10 Percentile:48.21(Engineering, Electrical & Electronic)

Cable-in-conduit conductors that consist of about 1,000 Nb$$_{3}$$Sn strands with an outer diameter of about 0.8mm, have been designed for the TF and CS coils of the ITER. The rated current of these coils is 40 -68kA. Two joint types (Butt and Lap) were developed during the CS Model Coil project. The performance of these joints was evaluated during the operating tests and the satisfied results were obtained. The joints of the TF coils are located outside of the winding in a region where the magnetic field is about 2.1T, a very low value as compared to the maximum field of 11.8T at the winding. The CS joints are located at the coil outer diameter and embedded within the winding pack due to the lack of the space. The maximum fields at the CS joint and winding are 3.5 and 13T, respectively. For the TF coils and the CS, the joints are cooled in series with the conductor at the outlet. The maximum temperature increase due to the joule heating in the joints is set at 0.15K to limit the heat load on the refrigerator. It is shown that both joint types are applicable to the ITER coils.

Journal Articles

Proposals for the final design of the ITER central solenoid

Yoshida, Kiyoshi; Takahashi, Yoshikazu; Mitchell, N.*; Bessette, D.*; Kubo, Hiroatsu*; Sugimoto, Makoto; Nunoya, Yoshihiko; Okuno, Kiyoshi

IEEE Transactions on Applied Superconductivity, 14(2), p.1405 - 1409, 2004/06

 Times Cited Count:16 Percentile:59.99(Engineering, Electrical & Electronic)

The ITER Central Solenoid (CS) is 12m high and 4m in diameter. The CS consists of a stack of 6electrically independent modules to allow control of plasma shape. The modules are compressed vertically by a pre-compression structure to maintain contact between modules. The CS conductor is CIC conductor with Nb$$_{3}$$Sn strands and a steel conduit. The CS model coil and insert coil test results have shown that the conductor design must be modified to achieve an operation margin. This required either to increase the cable diameter or to use strand with a higher current capability. A bronze-process (NbTi)$$_{3}$$Sn strand is proposed to achieve a higher critical magnetic field. A square conduit with a high Mn stainless steel is proposed as it can satisfy fatigue requirements. The inlets are in the high stress region and any stress intensification there must be minimized. The pre-compression structure is composed of 9tie plates to reduce the stress on the cooling pipes. These design proposals satisfy all ITER operational requirements.

Journal Articles

Experimental results of ITER Nb$$_{3}$$Al insert; Characteristics of acoustic emission

Ninomiya, Akira*; Arai, Kazuaki*; Takano, Katsutoshi*; Tsugawa, Kazuhito*; Ishigooka, Takeshi*; Kaiho, Katsuyuki*; Nakajima, Hideo; Okuno, Kiyoshi; CS Model Coil Test Group

Teion Kogaku, 38(8), p.425 - 433, 2003/08

The charge test of Central Solenoid Model Coil(CSMC) and Toroidal Field Insert Coil(TFIC) were carried out fo about one month from September 2001 with international collaboration under ITER EDA. In the experiment, Acoustic Emission(AE) signals were measured which were induced from CSMC and TFIC. It was the first trial to measure the AE signals from the insert coil directly. Relations among AE signals from TFIC, intensity, number and voltages are discussed in this paper.

Journal Articles

Development of ITER toroidal field insert; International collaboration with Russia

Sugimoto, Makoto; Nakajima, Hideo; Kato, Takashi; Okuno, Kiyoshi; Tsuji, Hiroshi; Rodin, I.*; Egorov, S. A.*

Teion Kogaku, 37(10), p.513 - 522, 2002/10

The Central Solenoid (CS) model coil programme has been carrying out since 1992 as a back born project in International Thermonuclear Experimental Reactor (ITER) Engineering Design Activity (EDA). The CS model coil programme has a plan to develop the toroidal fieled (TF) insert to demonstrate the conductor performance of ITER real TF coils under 13 T of magnetic flux density. The fabrication of TF insert was completed on May 2001 by D.V.Efremov Scientific Research Institute for Electrophysical Apparatus(Efremov institute) at St. Petersburg, Russia. Experiments including the cooldown and warmup were completed November 2001 at JAERI Naka. TF insert was achieved to charge up to 13T with 46kA without training under the back up magnetic field by the CS model coil.

Journal Articles

Development of high Cu ratio Nb$$_{3}$$Al and Nb$$_{3}$$Sn CICCs for superconducting toroidal field coils of JT-60

Kizu, Kaname; Miura, Yushi; Tsuchiya, Katsuhiko; Matsui, Kunihiro; Isono, Takaaki; Sakasai, Akira; Matsukawa, Makoto; Ishida, Shinichi; Ando, Toshinari

IEEE Transactions on Applied Superconductivity, 12(1), p.575 - 578, 2002/03

 Times Cited Count:9 Percentile:47.86(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Development of Nb$$_{3}$$Sn and NbTi CIC conductors for supercoducting poloidal field coils of JT-60

Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Isono, Takaaki; Matsui, Kunihiro; Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Ando, Toshinari

IEEE Transactions on Applied Superconductivity, 12(1), p.611 - 614, 2002/03

 Times Cited Count:8 Percentile:45.33(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Pulsed field losses and coupling current loop in a large current superconductor

Shimamoto, Susumu*; Murase, Satoru*; Nishii, Kenji*; Naito, Fuminobu*; Matsui, Kunihiro; Takahashi, Yoshikazu; Tsuji, Hiroshi

Denki Gakkai Rombunshi, B, 122(1), p.58 - 63, 2002/01

no abstracts in English

Journal Articles

Progress of the ITER central solenoid model coil programme

Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.

Nuclear Fusion, 41(5), p.645 - 651, 2001/05

 Times Cited Count:57 Percentile:83.02(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Current distribution and strain influence on the electromagnetic performance of the CS insert

Galindo, V.*; Ciarynski, D.*; Duchateau, J. L.*; Nishijima, Gen; Koizumi, Norikiyo; Takahashi, Yoshikazu; Ando, Toshinari

IEEE Transactions on Applied Superconductivity, 11(1), p.1538 - 1541, 2001/03

 Times Cited Count:12 Percentile:57.85(Engineering, Electrical & Electronic)

no abstracts in English

JAEA Reports

Annual report of Naka Fusion Research Establishment from April 1, 1999 to March 31, 2000

Naka Fusion Research Establishment

JAERI-Review 2000-030, 113 Pages, 2001/01

JAERI-Review-2000-030.pdf:10.11MB

no abstracts in English

Journal Articles

Vibration analysis in JT-60SU design

Ushigusa, Kenkichi; Isayama, Akihiko; Kurita, Genichi; Ishida, Shinichi; Neyatani, Yuzuru; Ishiyama, Shintaro; Kikuchi, Mitsuru; Otsuka, M.*; Sasaki, T.*; Nakagawa, S.*; et al.

Fusion Engineering and Design, 51-52, p.371 - 376, 2000/11

 Times Cited Count:1 Percentile:12.1(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of a 13T-640MJ superconducting pulsed coil for fusion machines

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

Denki Gakkai Rombunshi, B, 120(3), p.449 - 456, 2000/03

no abstracts in English

Journal Articles

Completion of CS insert fabrication

Sugimoto, Makoto; Isono, Takaaki; Nunoya, Yoshihiko; Koizumi, Norikiyo; Nakajima, Hideo; Kato, Takashi; Matsukawa, Makoto; Hamada, Kazuya; Matsui, Kunihiro; Nishijima, Gen; et al.

IEEE Transactions on Applied Superconductivity, 10(1), p.564 - 567, 2000/03

 Times Cited Count:22 Percentile:71.03(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Completion of the ITER CS model coil-outer module fabrication

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

IEEE Transactions on Applied Superconductivity, 10(1), p.568 - 571, 2000/03

 Times Cited Count:10 Percentile:53.54(Engineering, Electrical & Electronic)

no abstracts in English

54 (Records 1-20 displayed on this page)