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Comparative studies of three-dimensional analysis and measurement for establishing pulse electromagnet design

高柳 智弘; 植野 智晶*; 堀野 光喜*; 小野 礼人; 山本 風海; 金正 倫計

IEEE Transactions on Applied Superconductivity, 30(4), p.4901605_1 - 4901605_5, 2020/06

 被引用回数:0 パーセンタイル:100(Engineering, Electrical & Electronic)

A new horizontal shift bump magnet for the J-PARC RCS injection system was designed and fabricated. The magnet is a pulse magnet that repeatedly excites a trapezoidal waveform of about 1.5ms at 25Hz with the maximum current of 16kA and the voltage of 12kV. In order to design the magnets of such specifications, three-dimensional analysis of time-varying magnetic field which capable of evaluating eddy currents is required. Using one electromagnet model, the difference between the static magnetic field analysis and the dynamic magnetic field analysis, and the difference between the two-dimensional and three-dimensional analysis were compared, respectively. In addition, we also verified the analysis result and the actual measurement results carried out by the search coil and the hall probe. Finally, we established a pulse electromagnet design method. The verification results by the fabricated electromagnet are presented here.


A New pulse magnet for the RCS injection shift bump magnet at J-PARC

高柳 智弘; 山本 風海; 神谷 潤一郎; Saha, P. K.; 植野 智晶*; 堀野 光喜*; 金正 倫計; 入江 吉郎*

IEEE Transactions on Applied Superconductivity, 28(3), p.4100505_1 - 4100505_5, 2018/04

The 3-GeV Rapid-Cycling Synchrotron at the Japan Proton Accelerator Research Complex has demonstrated a high power beam equivalent to 1 MW. Therefore, in order to realize more stable operation, we are considering an upgrade plan. Regarding the radiation protection at the upgrade plan, a new injection system has been proposed to secure enough space for radiation shielding and maintenance work. For this purpose, it is necessary to integrate the splitted iron cores of the injection shift bump magnet into one core, the length of which is shorter than the total length of the splitted iron cores. The number of coil turns for the new one core magnet is then increased from 2 to 4. The structural design of the new shift bump magnet excited at 25 Hz repetition rate is in progress from view point of eddy current losses at the magnet edge and the coil temperature by using the OPERA-3D. This paper details these aspects and outlines the new power supply briefly.


Evaluation of thermal strain induced in components of Nb$$_{3}$$Sn strand during cooling

諏訪 友音*; 辺見 努*; 齊藤 徹*; 高橋 良和*; 小泉 徳潔*; Luzin, V.*; 鈴木 裕士; Harjo, S.

IEEE Transactions on Applied Superconductivity, 28(3), p.6001104_1 - 6001104_4, 2018/04

 被引用回数:0 パーセンタイル:100(Engineering, Electrical & Electronic)

Nb$$_{3}$$Sn strands, whose properties are very sensitive to stress/strain, are utilized for ITER cable-in-conduit conductor (CICC) of the central solenoids. The Nb$$_{3}$$Sn strands experience temperature range of $$sim$$1000 K from the temperature of the heat treatment with the initiation of the Nb$$_{3}$$Sn reaction to the operation temperature of $$sim$$4 K. Due to this large temperature range, large thermal strain is induced in the Nb$$_{3}$$Sn filaments due to the differences between the coefficients of thermal expansion and Young's moduli of the components of the strand. Therefore, it is considered that initial performance of the CICC is influenced by the thermal strain on the Nb$$_{3}$$Sn, and it is important to evaluate the strain state of the Nb$$_{3}$$Sn strand at low temperature. In this study, the thermal strain of the components of free Nb$$_{3}$$Sn strand was measured by neutron diffraction and stress/strain state was assessed from room temperature to low temperature. As the results of diffraction measurements, it was found that 0.111 % and 0.209 % compressive strain were generated in Nb$$_{3}$$Sn filaments at 300 and 10 K, respectively.


Beamline test of a transition-edge-sensor spectrometer in preparation for kaonic-atom measurements

橋本 直*; 谷田 聖; 他49名*

IEEE Transactions on Applied Superconductivity, 27(4), p.2100905_1 - 2100905_5, 2017/06

 被引用回数:6 パーセンタイル:41.84(Engineering, Electrical & Electronic)

We are developing a new technique to apply transition-edge sensors (TESs) to X-ray spectroscopy of exotic atoms, especially of kaonic atoms. To demonstrate the feasibility of this pioneering project, performance of a TES-based X-ray detector was evaluated in pion- and kaon-beam environments at particle accelerators. We successfully observed X-rays from pionic-carbon atoms with a resolution as good as 7 eV FWHM at 6 keV. Also at a kaon beamline, we confirmed that the TES spectrometer will be able to achieve our resolution goal, 6 eV, in our first scientific campaign to measure X-rays from kaonic-helium atoms.


Evaluation of bending strain in Nb$$_{3}$$Sn strands of CIC conductor using neutron diffraction

辺見 努*; Harjo, S.; 梶谷 秀樹*; 諏訪 友音*; 齊藤 徹*; 相澤 一也; 長村 光造*; 小泉 徳潔*

IEEE Transactions on Applied Superconductivity, 27(4), p.4200905_1 - 4200905_5, 2017/06

The superconducting property of Nb$$_{3}$$Sn strands is very sensitive to strain. The transverse electromagnetic loading has been considered as a major origin of the degradation of Nb$$_{3}$$Sn cable-in-conduit conductors (CICCs) due to the local bending. Since the bending pitch is around 5 mm due to contacting of strands compacted by the electromagnetic transverse loading, there is a possibility of a large bending strain with small deflection of strands. The bending strain of the strands cannot be evaluated from only the small deflection obtained visually. Measuring bending strain of Nb$$_{3}$$Sn strand in CICCs is important for evaluating the conductor performance. Neutrons, which have a large penetration depth, are a powerful tool to evaluate the internal strain of Nb$$_{3}$$Sn in the CICC. This paper shows that the bending strain in Nb$$_{3}$$Sn strands of CICCs can be determined by the neutron diffraction profile nondestructively and quantitatively.


Analysis of maximum voltage transient of JT-60SA toroidal field coils in case of fast discharge

Novello, L.*; Cara, P.*; Coletti, A.*; Gaio, E.*; Maistrello, A.*; 松川 誠; Philipps, G.*; Tomarchio, V.*; 山内 邦仁

IEEE Transactions on Applied Superconductivity, 26(2), p.4700507_1 - 4700507_7, 2016/03

 被引用回数:4 パーセンタイル:60.5(Engineering, Electrical & Electronic)

The voltage transient appearing across and inside the toroidal field (TF) coils of JT-60SA in case of fast voltage variation, such as a safety discharge operated by the quench protection circuit (QPC), can be significantly high. In fact, the voltage distribution between coils and inside the winding can be not uniform during fast transient, being influenced by the presence of parasitic capacitances. A simplified electrical model of the TF coils has been developed to investigate this aspect. The obtained model has been used in conjunction with an electrical model of the TF circuit elements, including a simplified model of the QPC. The worst case in terms of transient voltage applied to the winding has been identified, corresponding to a fault to ground occurring just after QPC operation. It has been verified that the resulting voltage is largely inside the coil insulation capability defined by performed insulation voltage tests.


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

高橋 良和; 諏訪 友音; 名原 啓博; 尾関 秀将; 辺見 努; 布谷 嘉彦; 礒野 高明; 松井 邦浩; 河野 勝己; 押切 雅幸; et al.

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

 被引用回数:0 パーセンタイル:100(Engineering, Electrical & Electronic)

原子力機構はITER中心ソレノイド(CS)コイル用導体の調達を担当し、製作したCS導体をコイル製作担当の米国に送付することになっている。CSコイルは高さ約12m、外径約4mで、6個のモジュールを積み重ねた構造を有する。導体の単長は最大910mであり、通電電流値は13Tの磁場中において40kAである。導体はケーブル・イン・コンジット型と呼ばれるもので、576本のNb$$_{3}$$Sn素線と288本の銅素線で構成される撚線を、矩形の中に円形の穴がある高マンガン鋼(JK2LB)製ジャケットに挿入し、ジャケットを圧縮成型したものである。圧縮成型される前のジャケットは、外寸法51.3mm、穴の直径35.3mm、単長7m、重さ約90kgである。このジャケットは、出荷前に非破壊検査により、最大許容サイズの欠陥がないことを確認する必要がある。内及び外表面の欠陥は、渦電流探傷(ECT)法 で、内部の欠陥は、超音波探傷(UT)法で行われる。UTにおいて、矩形の中に円形の穴がある形状であるので、超音波の入射の方向を工夫する必要があった。表面のECT及び内部のUTについて、その技術と検査実績を報告する。


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

名原 啓博; 諏訪 友音; 高橋 良和; 辺見 努; 梶谷 秀樹; 尾関 秀将; 櫻井 武尊; 井口 将秀; 布谷 嘉彦; 礒野 高明; et al.

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

 被引用回数:0 パーセンタイル:100(Engineering, Electrical & Electronic)

JAEA procures all superconductors for central solenoid (CS) in the ITER project. The cable is inserted into a conduit and compacted with it. During the insertion, the number of the rotation at the point ($$N_{p}$$) of the TF cable increased linearly to 50 against the inserted cable length ($$l_{i}$$). At first, $$N_{p}$$ of the CS cable also increased linearly by $$l_{i}$$ of 150 m. However, the increasing rate declined and the $$N_{p}$$ became constant to 30 at 600 m. During the compaction, the number of the rotation at the tail ($$N_{t}$$) of the CS cable increased linearly to 69 against the compacted cable length ($$l_{c}$$). It is important to measure not only $$N_{p}$$ but also $$N_{t}$$ because the rotation affects the twist pitch of the cable ($$l_{p}$$). After manufacturing the CS conductor, an X-ray transmission imaging made clear the $$l_{p}$$ along the whole length of the conductor for the first time. The $$l_{p}$$ peaked at the point; thus, a conductor sample should be taken there to investigate the effect of the $$l_{p}$$ elongation on the conductor performance.


Development of Terminal Joint and Lead Extension for JT-60SA Central Solenoid

村上 陽之; 木津 要; 市毛 寿一; 古川 真人; 夏目 恭平; 土屋 勝彦; 神谷 宏治; 小出 芳彦; 吉田 清; 尾花 哲浩*; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4201305_1 - 4201305_5, 2015/06

 被引用回数:6 パーセンタイル:54.28(Engineering, Electrical & Electronic)



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

尾関 秀将; 礒野 高明; 河野 勝己; 齊藤 徹; 川崎 勉; 西野 克巳; 奥野 清; 木戸 修一*; 仙波 智行*; 鈴木 洋三*; et al.

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

 被引用回数:0 パーセンタイル:100(Engineering, Electrical & Electronic)

JAEA is planning performance test of 50 m Toroidal Field (TF) conductor of ITER using Central Solenoid Model Coil (CSMC) test facility at Naka-site in Japan. In order to test the conductor, "TF Insert Coil" (TFIC) is under fabrication in cooperate with Hitachi, Ltd. TFIC is a solenoid coil wound in 1.44 m diameter. It is going to be installed into the bore of CSMC, whose maximum magnetic field is 13 T. The maximum driven current of TFIC is 68 kA. In order to prepare for fabrication of TFIC, several trials of components including windings, removal of Cr plating of the strands, welding and compaction of terminal sleeve were carried out for process qualification. The results of trials showed that the winding dimater satisfied its criterion, the Cr plating was clearly removed using non-woven cloth soaked into HCl solution, the mechanical strengths at 4 K of welds at the terminal were enough. Eventually, the fabrication process qualification of TFIC was completed.


Evaluation of temperature rise caused by AC loss due to plasma disruption in joint of JT-60SA poloidal field coil

中村 一也*; 山本 侑祐*; Suzuki, K.*; 高尾 智明*; 村上 陽之; 夏目 恭平; 吉田 清

IEEE Transactions on Applied Superconductivity, 25(3), p.4200704_1 - 4200704_4, 2015/06

 被引用回数:0 パーセンタイル:100(Engineering, Electrical & Electronic)

The JT-60 Super Advanced (JT-60SA) of Japan Atomic Energy Agency is a fusion experiment device designed to contribute to the early realization of fusion energy by providing support to the operation of ITER. The CS and EF coils are fabricated in Japan. In case of the butt joint for CS, two conductors are pressed onto each side of a copper sheet. As for the lap joint, two conductors are pressed by overlapping them with copper blocks for used EF pancake coils and between the CS and the current feeder. When a time-varying magnetic field is applied to the joints, an AC loss occurs, and temperature margin of the joint decreases due to the AC loss. It is necessary to understand the temperature margin of the joints to protect this coil system from quench. In this study, we fabricated the butt joint and lap joint, and measured the AC losses under the time varying field. Based on these experimental results, we analyzed the temperature rise caused by AC losses of the joints by using FEM under the standard plasma scenario and disruption scenario. The obtained results become fundamental data to estimate the temperature margin of the joints.


Model magnet development of D1 beam separation dipole for the HL-LHC upgrade

中本 建志*; 菅野 未知央*; Xu, Q.*; 川又 弘史*; 榎本 瞬*; 東 憲男*; 出崎 亮; 飯尾 雅実*; Ikemoto, Yukio*; 岩崎 るり*; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4000505_1 - 4000505_5, 2015/06

近年、大強度加速器施設におけるビーム高強度化を実現するため、強い放射線環境下で安定に高磁場を形成可能な超伝導磁石システムが求められている。本研究では、大型ハドロン衝突型加速器(Large Hadron Collider: LHC)の高輝度化アップグレード計画において、数十MGy級の耐放射線性を有するビーム分離用双極超伝導磁石システム(D1システム)を開発することを目指している。このシステムには超伝導材料や電気絶縁材料が用いられるが、電気絶縁材料にはコイル線材間の隙間を埋める成形性と十分な耐放射線性が要求される。我々は高い成形性、放射線照射時の低分解ガス生成能と高強度維持を実現したガラス繊維強化ビスマレイミドトリアジン(BT)樹脂を開発した。従来のガラス繊維強化エポキシ(G10)樹脂の場合、10MGyの$$gamma$$線照射後、4$$times$$10$$^{-5}$$mol/gのガスが発生し、曲げ強度が初期値の60%である280MPaまで低下したのに対し、BTでは100MGyの$$gamma$$線照射後、5$$times$$10$$^{-5}$$mol/gのガス発生量と初期値の90%である640MPaの曲げ強度を示した。今後、NbTi系超伝導線材の開発と磁石デザインを行ない、D1システム用モデル磁石を製作する予定である。


Influence of discontinuous columnar defects on flux pinning properties in GdBCO coated conductors

末吉 哲郎*; 上滝 哲也*; 古木 裕一*; 浦口 雄世*; 甲斐 隆史*; 藤吉 孝則*; 嶋田 雄介*; 安田 和弘*; 石川 法人

IEEE Transactions on Applied Superconductivity, 25(3), p.6603004_1 - 6603004_4, 2015/06

 被引用回数:6 パーセンタイル:54.28(Engineering, Electrical & Electronic)

GdBCOコート線材に導入した不連続柱状欠陥による磁束ピン止め特性への影響を、連続柱状欠陥による影響と比較することによって明らかにした。具体的には、270MeV Xeイオン照射効果と80MeV Xeイオン照射効果を比較した。前者の場合、連続的な柱状欠陥を導入することができ、後者の場合不連続的な柱状欠陥が形成されることを、透過型電子顕微鏡観察により確認した。それぞれのイオン照射による臨界電流密度(Jc)の上昇を比較した結果、以下のことが分かった。前者の場合、柱状欠陥の導入方向と同じ方向に磁場が向いているときに、最もJcの上昇が顕著にみられ、磁場角度依存性曲線において未照射試料に見られなかったJcピークが現れた。この傾向は、後者の不連続柱状欠陥の場合にも同様に見られた。ただし、後者の場合には、柱状欠陥の導入方向以外の磁場角度においても、平均的なJcの上昇傾向がみられた。この傾向は、点状欠陥の場合でも見られており、不連続な柱状欠陥は、連続的な柱状欠陥と点状欠陥の影響を合わせ持つような効果を与えることが分かった。超伝導体の応用面からは、ある磁場角度に偏らない形でJcの大きな向上を図ることが望ましいため、不連続な柱状欠陥の導入は、材料設計上優れた手法であることが分かった。


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

名原 啓博; 辺見 努; 梶谷 秀樹; 尾関 秀将; 諏訪 友音; 井口 将秀; 布谷 嘉彦; 礒野 高明; 松井 邦浩; 小泉 徳潔; et al.

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



Investigation of strand bending in the He-inlet during reaction heat treatment for ITER TF Coils

辺見 努; 松井 邦浩; 梶谷 秀樹; 奥野 清; 小泉 徳潔; 石見 明洋; 勝山 幸三

IEEE Transactions on Applied Superconductivity, 24(3), p.4802704_1 - 4802704_4, 2014/06

 被引用回数:0 パーセンタイル:100(Engineering, Electrical & Electronic)



Establishment of production process of JK2LB jacket section for ITER CS

尾関 秀将; 濱田 一弥; 高橋 良和; 布谷 嘉彦; 河野 勝己; 押切 雅幸; 齊藤 徹; 手島 修*; 松並 正寛*

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

 被引用回数:13 パーセンタイル:33.4(Engineering, Electrical & Electronic)

JAEA is in charge of procuring Center Solenoid (CS) conductor in ITER project. CS conductor is Cable-In-Conduit type, and conduit is also called jacket. The cross-sectional shape of CS jacket is circle-in-square type, whose outer dimension is 51.3 mm and inner diameter is 35.3 mm. The length of one CS jacket section is 7 m, and the necessary total length of CS conductor is about 43 km. CS coil is expected to suffer high electro-magnetic force, so JAEA developed JK2LB, which is modified stainless steel expected to better characteristics of fatigue and thermal contraction in 4 K than SUS316LN, in cooperate with Kobe Steel, Ltd. The remaining problem was to establish production process of jackets which satisfy dimensional and mechanical requirement in ITER consistently, and also, Non-Destructive Examination (NDE) by ITER-original criteria. To carry out the R&D for above, production of dummy CS jackets were executed and these jackets were fabricated successfully. The results are reported.


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

高橋 良和; 名原 啓博; 尾関 秀将; 辺見 努; 布谷 嘉彦; 礒野 高明; 松井 邦浩; 河野 勝己; 押切 雅幸; 宇野 康弘; et al.

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

 被引用回数:17 パーセンタイル:26.05(Engineering, Electrical & Electronic)



Progress of manufacturing trials for the ITER toroidal field coil structures

井口 将秀; 森本 将明; 千田 豊*; 辺見 努; 中嶋 秀夫; 中平 昌隆; 小泉 徳潔; 山本 暁男*; 三宅 孝司*; 澤 直樹*

IEEE Transactions on Applied Superconductivity, 24(3), p.3801004_1 - 3801004_4, 2014/06

 被引用回数:6 パーセンタイル:55.66(Engineering, Electrical & Electronic)



Mass production of superconducting magnet components for JT-60SA

吉田 清; 村上 陽之; 木津 要; 土屋 勝彦; 神谷 宏治; 小出 芳彦; Phillips, G.*; Zani, L.*; Wanner, M.*; Barabaschi, P.*; et al.

IEEE Transactions on Applied Superconductivity, 24(3), p.4200806_1 - 4200806_6, 2014/06

 被引用回数:13 パーセンタイル:33.4(Engineering, Electrical & Electronic)



Development and test of JT-60SA central solenoid model coil

村上 陽之; 木津 要; 土屋 勝彦; 小出 芳彦; 吉田 清; 尾花 哲浩*; 高畑 一也*; 濱口 真司*; 力石 浩孝*; 夏目 恭平*; et al.

IEEE Transactions on Applied Superconductivity, 24(3), p.4200205_1 - 4200205_5, 2014/06

 被引用回数:20 パーセンタイル:22.03(Engineering, Electrical & Electronic)


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