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Iyota, Muneyoshi*; Matsuda, Tomoki*; Sano, Tomokazu*; Shigeta, Masaya*; Shobu, Takahisa; Yumoto, Hirokatsu*; Koyama, Takahisa*; Yamazaki, Hiroshi*; Semba, Yasunori*; Ohashi, Haruhiko*; et al.
Journal of Manufacturing Processes, 94, p.424 - 434, 2023/05
Times Cited Count:7 Percentile:72.06(Engineering, Manufacturing)Kashiwagi, Mieko; Umeda, Naotaka; Tobari, Hiroyuki; Kojima, Atsushi; Yoshida, Masafumi; Taniguchi, Masaki; Dairaku, Masayuki; Maejima, Tetsuya; Yamanaka, Haruhiko; Watanabe, Kazuhiro; et al.
Review of Scientific Instruments, 85(2), p.02B320_1 - 02B320_3, 2014/02
Times Cited Count:29 Percentile:73.28(Instruments & Instrumentation)The negative ion extractor for high power and long-pulse operations is newly developed toward the neutral beam injector (NBI) for heating & current drive of future fusion machines such as ITER, JT-60 Super Advanced (SA) and DEMO reactor. The satisfactory cooling capability is designed in the thermal analysis. A negative ion production and a suppression of electrons are experimentally validated for this new extractor. As the results, the negative ion current shows increases by a factor of 1.3 with suppressing the electron current. The beam divergence angle is also maintained small enough, 4 mrad.
Umeda, Naotaka; Kashiwagi, Mieko; Taniguchi, Masaki; Tobari, Hiroyuki; Watanabe, Kazuhiro; Dairaku, Masayuki; Yamanaka, Haruhiko; Inoue, Takashi; Kojima, Atsushi; Hanada, Masaya
Review of Scientific Instruments, 85(2), p.02B304_1 - 02B304_3, 2014/02
Times Cited Count:13 Percentile:48.74(Instruments & Instrumentation)In order to realize neutral beam systems in ITER whose target is to produce D ion beam of 1 MeV, 200 A/m
during 3600s, the electrostatic five-stages negative ion accelerator has been developed at JAEA. To extend pulse length, heat load of the acceleration grids was reduced by controlling the ion beam trajectory. Namely, the beam deflection due to the residual magnetic filter in the accelerator was suppressed with the newly developed extractor with a 0.5 mm off-set aperture displacement. The use of new extractor improved the deflection angle from 6 mrad to 1 mrad, resulting in the reduction of direct interception of negative ions from 23% to 15% of the total acceleration power, respectively. As a result, the pulse length of 130 A/m
, 881 keV H
ion beam has been successfully extended from a previous value of 0.4s to 8.7s.
Tobari, Hiroyuki; Inoue, Takashi; Taniguchi, Masaki; Kashiwagi, Mieko; Umeda, Naotaka; Dairaku, Masayuki; Yamanaka, Haruhiko; Watanabe, Kazuhiro; Sakamoto, Keishi; Kuriyama, Masaaki*; et al.
Fusion Engineering and Design, 88(6-8), p.975 - 979, 2013/10
Times Cited Count:1 Percentile:10.08(Nuclear Science & Technology)The HV bushing, one of the ITER NB components, which is to be procured by JADA, is a multi-conductor feed through composed of five-stage double-layered insulator columns with large brazed ceramic ring and fiber reinforced plastic (FRP) ring. The HV bushing is a bulk head between insulation gas at 0.6 MPa and vacuum. The FRP ring is required to sustain the pressure load, seismic load and dead weight. Brazing area of the ceramic ring with Kovar is required to maintain vacuum leak tightness and pressure tightness against the air filled at 0.6 MPa. To design the HV bushing satisfying the safety factor of 3.5, mechanical analyses were carried out. As for the FRP ring, it was confirmed that isotropic fiber cloth FRP rings should be used for sufficient strength against shear stress. Also, shape and fixation area of the Kovar sleeve were modified to lower the stress at the joint area. As a result, a design of the insulator for the HV bushing was established satisfying the requirement.
Kashiwagi, Mieko; Taniguchi, Masaki; Umeda, Naotaka; Dairaku, Masayuki; Tobari, Hiroyuki; Yamanaka, Haruhiko; Watanabe, Kazuhiro; Inoue, Takashi; DeEsch, H. P. L.*; Grisham, L. R.*; et al.
AIP Conference Proceedings 1515, p.227 - 236, 2013/02
Times Cited Count:12 Percentile:95.67(Physics, Applied)In a five stage multi-aperture multi-grid (MAMuG) accelerator for the ITER neutral beam injector (NBI), 1 MeV, 40 A D ion beam is required for 1 hour. However, beamlets are deflected due to (1) magnetic field for electron suppression and (2) space charge repulsion between beamlets, and consequently, cause excess grid heat load. A three dimensional beam analysis has been carried out to compensate the beamlet deflections. This paper shows that the beamlet deflections due to (1) and (2) are compensated by an aperture offset of only 0.6 mm applied to the aperture of 17 mm in diameter in the extractor and by a metal bar attached around aperture area beneath the extractor, respectively. When the metal bar is increased to 3 mm in thickness and installed 30 mm away from the aperture area, the beamlet is steered gently by the weaker electric field distortion. The beam optics was confirmed not deteriorated by those compensations. The presentation also discusses application of these compensation techniques to the ITER design.
Tobari, Hiroyuki; Taniguchi, Masaki; Kashiwagi, Mieko; Dairaku, Masayuki; Umeda, Naotaka; Yamanaka, Haruhiko; Tsuchida, Kazuki; Takemoto, Jumpei; Watanabe, Kazuhiro; Inoue, Takashi; et al.
Plasma Science and Technology, 15(2), p.179 - 183, 2013/02
Times Cited Count:1 Percentile:4.17(Physics, Fluids & Plasmas)Vacuum insulation is a common issue for the accelerator and the HV bushing for the ITER NBI. The HV bushing has five-stage structure and each stage consists of double-layered insulators. Hence, several triple points exist around the insulators. To reduce electric field at those points simultaneously, three types of stress ring were developed. In voltage holding test of a full-scale mockup equipped with those stress rings, 120% of rated voltage was sustained and the voltage holding capability required in ITER was verified. In the MeV accelerator, voltage holding capability was not sufficient due to breakdown triggered by electric field concentration at edge and corner on grid components. By extending gap length, 1 MV was sustained in vacuum. Furthermore, with new accelerator grids which compensates beam deflection due to magnetic field and space charge repulsion between beamlets, 980 keV, 185 A/m H
ion beam acceleration was demonstrated, which was close to ITER requirement.
Taniguchi, Masaki; Kashiwagi, Mieko; Umeda, Naotaka; Dairaku, Masayuki; Takemoto, Jumpei; Tobari, Hiroyuki; Tsuchida, Kazuki; Yamanaka, Haruhiko; Watanabe, Kazuhiro; Kojima, Atsushi; et al.
Review of Scientific Instruments, 83(2), p.02B121_1 - 02B121_3, 2012/02
Times Cited Count:11 Percentile:45.39(Instruments & Instrumentation)JAEA has developed the MeV accelerator to demonstrate 1 MeV, 200 A/m H
ion beam acceleration required for ITER NBI. A key to realize such a high power accelerator is improvement of voltage holding capability. Based on detailed investigation of the voltage holding characteristics, MeV accelerator was modified to reduce electric field concentration by extending gaps between the grid supports and increasing curvature radiuses at the support corners. After the modifications, accelerator succeeded in sustaining -1 MV in vacuum without beam acceleration. Moreover, beam deflection due to the magnetic field for electron suppression and space charge repulsion was compensated by aperture displacement technique. As the result, beam deflection was compensated and voltage holding during the beam acceleration was improved. Beam parameter of the MeV accelerator was increased to 980 keV, 185 A/m
, which is close to the requirement of ITER accelerator.
Taniguchi, Masaki; Kashiwagi, Mieko; Inoue, Takashi; Umeda, Naotaka; Watanabe, Kazuhiro; Tobari, Hiroyuki; Dairaku, Masayuki; Yamanaka, Haruhiko; Tsuchida, Kazuki; Kojima, Atsushi; et al.
AIP Conference Proceedings 1390, p.449 - 456, 2011/09
Times Cited Count:2 Percentile:52.46(Physics, Atomic, Molecular & Chemical)At JAEA, MeV accelerator has been developed as a proof-of-principle accelerator for ITER NBI. To achieve the acceleration of 1 MeV, 200 A/m beam required for ITER, improvement of the voltage holding capability is essential. Review of voltage holding results ever obtained with various geometries of the accelerators showed that voltage holding capability was about a half of that for ideal small electrode. This is due to local electric field concentration in the accelerators, such as edge and corner between grids and its support structures. Based on these results, accelerator was modified to reduce the electric field concentration by reshaping the support structures and expanding the gap length. After the modifications, voltage holding capability in vacuum was increased from 835 kV to 1 MV. Voltage holding progressed the energy and current to 879 keV, 0.36 A (157 A/m
).
Kashiwagi, Mieko; Inoue, Takashi; Taniguchi, Masaki; Umeda, Naotaka; Grisham, L. R.*; Dairaku, Masayuki; Takemoto, Jumpei; Tobari, Hiroyuki; Tsuchida, Kazuki; Watanabe, Kazuhiro; et al.
AIP Conference Proceedings 1390, p.457 - 465, 2011/09
Times Cited Count:9 Percentile:88.26(Physics, Atomic, Molecular & Chemical)In a five stage multi-aperture and multi-grid (MAMuG) accelerator in JAEA, beam acceleration tests are in progress toward 1 MeV, 200 A/m H
ion beams for ITER. The 1 MV voltage holding has been successfully demonstrated for 4000 s with the accelerator of expanded gap length that lowered local electric field concentrations. The led to increase of the beam energy up to 900 keV-level. However, it was found that beamlets were deflected more in long gaps and direct interceptions of the deflected beamlet caused breakdowns. The beamlet deflection and its compensation methods were studied utilizing a three-dimensional multi beamlet analysis. The analysis showed that the 1 MeV beam can be compensated by a combination of the aperture offset of 0.8 mm applied in the electron suppression (ESG) and the metal bar called a field shaping plate with a thickness of 1 mm attached beneath the ESG. The paper reports analytical predictions and experimental results of the MAMuG accelerator.
Tsuchida, Kazuki; Watanabe, Kazuhiro; Tobari, Hiroyuki; Takemoto, Jumpei; Yamanaka, Haruhiko; Inoue, Takashi
Denki Gakkai Kenkyukai Shiryo, Genshiryoku Kenkyukai (NE-11-001004
006
010), p.17 - 22, 2011/09
A 1 MeV high-energy neutral beam injector is under developing for heating and current drive of ITER plasma in collaboration with EUDA. JADA will provide ultra-high voltage DC power supply components. Design of the 1 MV power supply, R&Ds on a HV bushing and a water choke will be presented. These results satisfy the requirements for the NBI system.
Kashiwagi, Mieko; Taniguchi, Masaki; Kojima, Atsushi; Dairaku, Masayuki; Hanada, Masaya; Hemsworth, R. S.*; Mizuno, Takatoshi*; Takemoto, Jumpei; Tanaka, Masanobu*; Tanaka, Yutaka*; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2011/03
At JAEA, a multi-aperture multi-grid accelerator has been developed for the ITER neutral beam system. A target is H ion beam acceleration of 0.5 A (200 A/m
) at 1 MeV. In real accelerators, it was found that the voltage holding was about a half of that obtained in an ideal small electrode. After applying necessary gap length and radii of edges of grid supports to lower local electric field concentrations, the accelerator succeeded in sustaining 1 MV for 4000 s. As a result, beam parameters were increased to 879 keV, 0.36 A (157 A/m
) at perveance matched condition from 796 kV, 0.32 A (140 A/m
) reported in FEC2008. In the beam acceleration, the beamlet deflections due to magnetic field and space charge repulsion caused direct interceptions, that resulted in limitations in the beam energy and current. Compensation of these beamlet deflections has been tested applying aperture offset and field shaping plate, which were examined in a three-dimensional beam analysis.
Tobari, Hiroyuki; Inoue, Takashi; Hanada, Masaya; Dairaku, Masayuki; Watanabe, Kazuhiro; Umeda, Naotaka; Taniguchi, Masaki; Kashiwagi, Mieko; Yamanaka, Haruhiko; Takemoto, Jumpei; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2011/03
High voltage (HV) bushing in the ITER NBI is one of critical components, which acts as a feedthrough for electric power and cooling water from the -1 MV power supply in SF gas to beam source inside vacuum. JAEA has overcome a longstanding issue on manufacturing of a large bore ceramic ring with 1.56 m in diameter as the insulator of the five-stage HV bushing. Joining method of the ceramic and metal flange with thick Kovar plate to form vacuum boundary was also developed. By assembling components, a full-size mockup bushing simulating one stage of the HV bushing was successfully manufactured. In the voltage holding test, the high voltage of 240 kV including the margin of 20 % of a rated voltage was sustained for 3600 s without breakdown, and the voltage holding capability required in ITER was successfully verified.
Yamamoto, Masanori; Watanabe, Kazuhiro; Yamanaka, Haruhiko; Takemoto, Jumpei; Yamashita, Yasuo*; Inoue, Takashi
JAEA-Technology 2010-029, 60 Pages, 2010/08
A power supply for the ITER Neutral Beam Injector (NBI) is a DC ultra-high voltage (UHV) power supply to accelerate negative ion beams of 40 A up to an energy of 1 MeV. Japan Atomic Energy Agency as the Japan Domestic Agency for ITER contributes procurement of dc -1 MV main components such as step-up -1 MV transformers rectifiers, a high voltage deck 2, a -1 MV insulating transformer, a transmission line, a surge reduction system and equipments for site test. Design of the surge suppression in the NBI power supply is one of the key issues to obtain the stable injector performance. This report describes the design study using EMTDC code on the surge suppression by optimizing the core snubber and additional elements in the -1 MV power supply. The results show that the input energy from the stray capacitance to the accelerator at the breakdown can be reduced to about 25 J that is smaller than the design criteria of 50 J for the ITER NBI.
Suzuki, Motofumi*; Tsukamoto, Takashi*; Inoue, Haruhiko*; Watanabe, Satoshi; Matsuhashi, Shimpei; Takahashi, Michiko*; Nakanishi, Hiromi*; Mori, Satoshi*; Nishizawa, Naoko*
Plant Molecular Biology, 66(6), p.609 - 617, 2008/04
Times Cited Count:139 Percentile:94.78(Biochemistry & Molecular Biology)Tobari, Hiroyuki; Taniguchi, Masaki; Kashiwagi, Mieko; Watanabe, Kazuhiro; Umeda, Naotaka; Dairaku, Masayuki; Yamanaka, Haruhiko; Inoue, Takashi
no journal, ,
The HV bushing, one of the ITER NB components which JADA procures, is a multi-conductor feedthrough composed of five-stage double-layered insulator columns with large brazed ceramic ring and fiber reinforced plastic (FRP) ring. The HV bushing is a bulk head between insulation gas and vacuum. Brazing area of the ceramic ring with Kovar is required to maintain vacuum leak tightness and pressure tightness against the air filled at 0.6 MPa. The FRP ring is required to support the pressure load, seismic load and dead weight. To design the HV bushing satisfying the safety factor of 3.5, mechanical analyses were carried out. As for the Kovar, thickness, shape and fixation of the Kovar sleeve were adjusted. As for the FRP ring, by using an isotropic fiber cloth FRP, sufficient strength was confirmed against shear stress. As a result, a design of the insulator for the HV bushing was established satisfying the requirement.
Taniguchi, Masaki; Umeda, Naotaka; Kashiwagi, Mieko; Inoue, Takashi; Watanabe, Kazuhiro; Tobari, Hiroyuki; Kojima, Atsushi; Dairaku, Masayuki; Yamanaka, Haruhiko; Hanada, Masaya
no journal, ,
Suppression of grid heat load by secondary particles is essential for the long pulse acceleration of 1 MeV, 200 A/m beam required for ITER NB. In the present work, the grid heat load in the MeV accelerator developed at JAEA is analyzed by EAMCC (Electrostatic Accelerator Monte Carlo Code). The EAMCC can calculate the grid heat load caused by the secondary electrons generated by the impact of the energetic particles onto the acceleration grids, and energetic atoms/ions generated through the process of the ion-residual gas molecules. As the result, it was found that (1) Decrease of grid thickness is effective to reduce the generation of secondary electrons by H
collision on aperture wall. (2) Decrease of aperture diameter was effective to suppress the heat load by stripped electrons, because most of the stripped electrons are removed before accelerating to full energy. By these modifications, grid heat load was decreased 30%.
Watanabe, Kazuhiro; Yamanaka, Haruhiko; Maejima, Tetsuya; Inoue, Takashi; Hanada, Masaya; Tanaka, Shigeru*; Kadowaki, Makoto*
no journal, ,
A DC -1 MV insulation transformer is required for ITER NBI power supply. However such insulation transformer has not been developed. Demonstration of the DC ultra high voltage insulation is essential to realize such insulation transformer. To demonstrate the insulation transformer, a transformer model has been designed and fabricated under the ITER research and development task. The high voltage test with the model has been successfully performed and it ensures that the real insulation transformer can be fabricated.
Tobari, Hiroyuki; Inoue, Takashi; Dairaku, Masayuki; Watanabe, Kazuhiro; Yamanaka, Haruhiko; Taniguchi, Masaki; Kashiwagi, Mieko; Umeda, Naotaka; Takemoto, Jumpei; Sakamoto, Keishi
no journal, ,
The HV bushing in the ITER NBI is a feedthrough for electric power and cooling water located between gas-insulated transmission line and a beam source in vacuum. The bushing has five-stage structure composed of large ceramic rings of which diameter must be 1.56 m to sustain electric insulation between conductors inside the ceramic. However, in conventional technique, the diameter has been limited less than 1 m. The brazing to form vacuum boundary for such a large ceramic ring with metal has not been established. Then, new forming method of the large ceramic ring and the brazing technique were developed. As a result, manufacturing of the ceramic ring and the brazing with to Kovar rings were accomplished. To enhance voltage holding capability of the insulator, stress ring to suppress the breakdown staring from the triple point was also developed. In the high voltage test of the insulator, 240 kV was sustained over 1 hour, and the voltage holding capability required in ITER was verified.
Inoue, Takashi; Dairaku, Masayuki; Kashiwagi, Mieko; Mizuno, Takatoshi; Taniguchi, Masaki; Tobari, Hiroyuki; Umeda, Naotaka; Watanabe, Kazuhiro; Yamanaka, Haruhiko
no journal, ,
Multiaperture multigrid accelerators and a HV bushing that connects power supply and the accelerator have been developed at JAEA for the ITER neutral beam injector (NBI). So far, the accelerator held dc 1 MV high voltage at operation pressure range of 0.1 Pa by lowering electric stress at cathode triple junction. Recently many discharge traces were found from small gaps, steps, corners, edges and even on screw heads suggesting discharges initiated from such local concentration of electric stresses. In order to mitigate the local stress gap between the accelerator grids were expanded from original 72 - 90 m to 100 mm. This was effective to improve the voltage holding even without hydrogen gas, and as the consequence, 360 mA H ions were accelerated up to 879 keV, which updated previous record of 796 keV, 320 mA.
Umeda, Naotaka; Kashiwagi, Mieko; Taniguchi, Masaki; Tobari, Hiroyuki; Watanabe, Kazuhiro; Yamanaka, Haruhiko; Dairaku, Masayuki; Inoue, Takashi; Kojima, Atsushi; Hanada, Masaya
no journal, ,
In JAEA, R&D of negative ion beam acceleration has been carried out using multi apertures and multi grids accelerator for realization of ITER neutral beam injector. High power negative ion beam acceleration of 0.98 MeV, 185 A/m has been achieved in 2011, but pulse duration time was restricted because of excess grid heat load. To reduce the grid heat load, beam deflection by residual filter magnet in the accelerator was corrected with newly developed extraction grid which had 0.5 mm aperture displacement. By the grid, beam deflection angle has been improved from 6 mrad to 1 mrad and grid heat load by direction interception of negative ion has reduced from 23% to 15%, respectively. This reads to long pulse beam acceleration of 0.88 MeV, 130 A/m
for 8.7s.