Spectroscopic measurement of increases in hydrogen molecular rotational temperature with plasma-facing surface temperature and due to collisional-radiative processes in tokamaks

N. Yoneda, T. Shikama, F. Scotti, K. Hanada, H. Iguchi, H. Idei, T. Onchi, A. Ejiri, T. Ido, K. Kono, Y. Peng, Y. Osawa, G. Yatomi, A. Kidani, M. Kudo, R. Hiraka, K. Takeda, R. E. Bell, A. Maan, D. P. BoyleR. Majeski, V. Soukhanovskii, M. Groth, A. McLean, R. S. Wilcox, C. Lasnier, K. Nakamura, Y. Nagashima, R. Ikezoe, M. Hasegawa, K. Kuroda, A. Higashijima, T. Nagata, S. Shimabukuro, I. Niiya, I. Sekiya, M. Hasuo

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Abstract

Spatially resolved rotational temperature of ground state hydrogen molecules desorbed from plasma-facing surface was measured in QUEST, LTX-β, and DIII-D tokamaks, and the increases of the rotational temperature with the surface temperature and due to collisional-radiative processes in the plasmas were evaluated. The increase due to collisional-radiative processes was calculated by solving rate equations considering electron and proton collisional excitation and deexcitation and spontaneous emission. The calculation results suggest a high sensitivity for the rotational temperature to electron and proton densities, but a negligible sensitivity to the electron, proton, and surface temperatures. In the three tokamaks with different plasma parameters and plasma-facing surface materials, the spatial profile of the rotational temperature was estimated using Fulcher-α emission lines (600-608 nm). In QUEST, the spatial profile of the rotational temperature was estimated from spatially resolved spectra. In the other tokamaks, the rotational temperature was evaluated assuming a single point emission with a location determined from the Fulcher-α emission profile as measured with a filtered camera. In metal-walled devices QUEST and LTX-β, the rotational temperature increased with the surface temperature, and the calculated collisional-radiative increase is consistent with measured increase assuming that the rotational temperature at the surface is approximately 500-600 K higher than the surface temperature. In DIII-D with carbon walls, a larger collisional-radiative increase than the other tokamaks was observed because of the higher density leading to a large difference from the calculated increase compared to the other smaller tokamaks. Measurement of the Fulcher-α emission profile with higher spatial resolution in DIII-D may reduce the difference and reveal the effect of the surface temperature on the rotational temperature. These results show the increases in the rotational temperature with the surface temperature and due to the collisional-radiative processes.

Original languageEnglish
Article number096004
JournalNuclear Fusion
Volume63
Issue number9
DOIs
StatePublished - Sep 2023

Funding

The first author is supported by Mori Manufacturing Research and Technology Foundation. The authors thank M. Ono for supporting the experiment in LTX-β, and T. Abrams for supporting the experiment in DIII-D. The authors are grateful to M. Čížek for providing the cross section data. The authors would like to thank the staff members of the machine shop of Kyoto University for their help with the fabrication of the spectroscopic system used in QUEST. This work was supported by bilateral collaboration programs of NIFS (NIFS19KUTR140, NIFS20KUTR156), Japan/U. S. Cooperation in Fusion Research and Development, and USDoE under contracts DE-AC52-07NA27344 (LLNL), DE-AC02-09CH11466 (Princeton University) and DE-AC05-00OR22725 (ORNL). This material is based upon work supported by the US. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Award(s) DE-FC02-04ER54698. The first author is supported by Mori Manufacturing Research and Technology Foundation. The authors thank M. Ono for supporting the experiment in LTX-β, and T. Abrams for supporting the experiment in DIII-D. The authors are grateful to M. Čížek for providing the cross section data. The authors would like to thank the staff members of the machine shop of Kyoto University for their help with the fabrication of the spectroscopic system used in QUEST. This work was supported by bilateral collaboration programs of NIFS (NIFS19KUTR140, NIFS20KUTR156), Japan/U. S. Cooperation in Fusion Research and Development, and USDoE under contracts DE-AC52-07NA27344 (LLNL), DE-AC02-09CH11466 (Princeton University) and DE-AC05-00OR22725 (ORNL). This material is based upon work supported by the US. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Award(s) DE-FC02-04ER54698.

FundersFunder number
Mori Manufacturing Research and Technology FoundationNIFS20KUTR156, NIFS19KUTR140
U.S. Department of EnergyDE-AC52-07NA27344
Office of ScienceDE-FC02-04ER54698
Fusion Energy Sciences
Lawrence Livermore National LaboratoryDE-AC02-09CH11466
Oak Ridge National Laboratory
Princeton UniversityDE-AC05-00OR22725

    Keywords

    • DIII-D
    • LTX-β
    • QUEST
    • emission spectroscopy
    • hydrogen molecule
    • plasma-surface interaction
    • rotational temperature

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