Performance of ITER pressure gauges during deuterium operation in the large helical device

被引:0
|
作者
Wenzel, Uwe [1 ]
Motojima, Gen [2 ]
Mackel, Felix [3 ]
Arkhipov, Alexey [4 ]
Jagielski, Bartholomew [6 ]
Haak, Victoria [1 ]
Meister, Hans [3 ]
Marquardt, Mirko [1 ]
Fox-Widdows, Ella [5 ]
机构
[1] Max Planck Inst Plasma Phys, D-17491 Greifswald, Germany
[2] Natl Inst Fus Sci, Toki Gifu 5095292, Japan
[3] Max Planck Inst Plasma Phys, D-85748 Greifswald, Germany
[4] Buhler Alzenau GmbH, D-63755 Alzenau, Germany
[5] Commonwealth Fus Syst, Devens, MA 01434 USA
[6] Univ Greifswald, D-17489 Greifswald, Germany
关键词
ITER; pressure gauges; LHD; neutrons;
D O I
10.1088/1361-6587/ad9059
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
During deuterium campaigns on the heliotron large helical device (LHD), ITER pressure gauges with different cathode materials were used to measure the neutral pressure in the sub-divertor region. Throughout these campaigns, it was observed that the performance of a LaB6 cathode was unsatisfactory during deuterium operation. Conversely, measurements taken with pressure gauges with a ZrC cathode performed well throughout the deuterium pulses. The ITER pressure gauge with the ZrC cathode could be operated with a very high electron current of 800 mu A, thus improving the lower detection limit of the neutral pressure in LHD. With this design it was also possible to avoid jumps in the ion current within strong magnetic fields, improving the accuracy of the measurement from 15% uncertainty to 5%. These features allowed very precise neutral pressure measurements to be made in a fusion device with magnetic confinement. The problems with the lifetime of the ZrC cathode reported in Mackel et al (2023 Fusion Eng. Des. 189 113439) were not relevant here, as the total runtime in the magnetic field was about 60 h, less than the expected lifetime of the cathode of 350 h.
引用
收藏
页数:8
相关论文
共 50 条
  • [31] Recent results from deuterium experiments on the large helical device and their contribution to fusion reactor development
    Osakabe, Masaki
    Takahashi, Hiromi
    Yamada, Hiroshi
    Tanaka, Kenji
    Kobayashi, Tatsuya
    Ida, Katsumi
    Ohdachi, Satoshi
    Varela, Jacobo
    Ogawa, Kunihiro
    Kobayashi, Masahiro
    Tsumori, Katsuyoshi
    Ikeda, Katsunori
    Masuzaki, Suguru
    Tanaka, Masahiro
    Nakata, Motoki
    Murakami, Sadayoshi
    Inagaki, Shigeru
    Mukai, Kiyofumi
    Sakamoto, Mizuki
    Nagasaki, Kazunobu
    Suzuki, Yasuhiro
    Isobe, Mitsutaka
    Morisaki, Tomohiro
    NUCLEAR FUSION, 2022, 62 (04)
  • [32] Neutron Emission Rate Characteristics of an Electron Cyclotron Heated Large Helical Device Deuterium Plasma
    Ogawa, Kunihiro
    Isobe, Mitsutaka
    Seki, Ryosuke
    Nuga, Hideo
    Sangaroon, Siriyaporn
    Jo, Jungmin
    Osakabe, Masaki
    PLASMA AND FUSION RESEARCH, 2021, 16 : 2402008 - 1
  • [33] Study of ion cyclotron range of frequencies heating characteristics in deuterium plasma in the Large Helical Device
    Kamio, S.
    Saito, K.
    Seki, R.
    Kasahara, H.
    Kanda, M.
    Nomura, G.
    Seki, T.
    NUCLEAR FUSION, 2022, 62 (01)
  • [34] Transport characteristics of deuterium and hydrogen plasmas with ion internal transport barrier in the Large Helical Device
    Nagaoka, K.
    Takahashi, H.
    Nakata, M.
    Satake, S.
    Tanaka, K.
    Mukai, K.
    Yokoyama, M.
    Nakano, H.
    Murakami, S.
    Ida, K.
    Yoshinuma, M.
    Ohdachi, S.
    Bando, T.
    Nunami, M.
    Seki, R.
    Yamaguchi, H.
    Osakabe, M.
    Morisaki, T.
    NUCLEAR FUSION, 2019, 59 (10)
  • [35] Observation of significant Doppler shift in deuterium-deuterium neutron energy caused by neutral beam injection in the large helical device
    Sangaroon, S.
    Ogawa, K.
    Isobe, M.
    Kobayashi, M. I.
    Fujiwara, Y.
    Kamio, S.
    Yamaguchi, H.
    Seki, R.
    Nuga, H.
    Takada, E.
    Murakami, S.
    Zhong, G. Q.
    Osakabe, M.
    AAPPS BULLETIN, 2022, 32 (01):
  • [36] Operation of the negative ion-based neutral beam injection system during Large Helical Device experimental campaigns
    Oka, Y
    Kaneko, O
    Takeiri, Y
    Tsumori, K
    Osakabe, M
    Ikeda, K
    Asano, E
    Kawamoto, T
    Akiyama, R
    Hamabe, M
    FUSION ENGINEERING AND DESIGN, 2001, 56-57 : 533 - 537
  • [37] Control of a steady-state operation using ICRF heating in the large helical device
    Kasahara, H.
    Seki, T.
    Saito, K.
    Kumazawa, R.
    Kubo, S.
    Shimozuma, T.
    Yoshimura, Y.
    Igami, H.
    Notake, T.
    Nakamura, Y.
    Miyazawa, J.
    Tanaka, K.
    Tokuzawa, T.
    Shimpo, F.
    Nomura, G.
    Yokota, M.
    Takahashi, C.
    Komori, A.
    Motojima, O.
    Mutoh, T.
    FUSION ENGINEERING AND DESIGN, 2008, 83 (2-3) : 253 - 255
  • [38] Cooldown performance of an inner vertical field coil for the large helical device
    Takahata, K
    Mito, T
    Satow, T
    Nishimura, A
    Yamada, S
    Yanagi, N
    Iwamoto, A
    Chikaraishi, H
    Imagawa, S
    Tamura, H
    Satoh, S
    Tanahashi, S
    Yamamoto, J
    Motojima, O
    Yamakoshi, T
    Yoshida, T
    Hanawa, S
    Kai, T
    IEEE TRANSACTIONS ON MAGNETICS, 1996, 32 (04) : 2252 - 2255
  • [39] Cooldown performance of an inner vertical field coil for the large helical device
    Natl Inst for Fusion Science, Gifu, Japan
    IEEE Trans Magn, 4 pt 1 (2252-2255):
  • [40] Regression Approach for Acquiring a Quantitative Guidance toward Updating the Deuterium-Deuterium Fusion Neutron Emission Rate in the Large Helical Device
    Ogawa, Kunihiro
    Yokoyama, Masayuki
    Isobe, Mitsutaka
    PLASMA AND FUSION RESEARCH, 2020, 15