4.5 Article

Plasma termination by excess pellet fueling and impurity injection in TJ-II, the Large Helical Device and Wendelstein 7-X

期刊

NUCLEAR FUSION
卷 59, 期 7, 页码 -

出版社

IOP PUBLISHING LTD
DOI: 10.1088/1741-4326/ab17fd

关键词

plasma termination; stellarator; W7-X; LHD; TJ-II

资金

  1. IEA Technology Collaboration Programme on the Stellarator-Heliotron Concept
  2. Euratom research and training programme 2014-2018 [633053]
  3. JSPS KAKENHI [23360415, 15H03759, 15H04234]
  4. Euratom research and training programme 2019-2020 [633053]
  5. fundamental budgetary support of the National Institute for Fusion Science [ULHH012, ULHH017]
  6. Program for Enhancing Research Collaboration of the National Institute for Fusion Science [UFEX105]
  7. Young Researchers Supporting Program of the National Institute for Fusion Science [UFEX106]
  8. NIFS/NINS under Strategic International Research Exchange Promotion Program [UFEX402]
  9. NINS program of Promoting Research by Networking among Institutions [01411702]
  10. MINECO [FIS2017-89326-F]
  11. Grants-in-Aid for Scientific Research [15H04234, 23360415, 15H03759] Funding Source: KAKEN

向作者/读者索取更多资源

Plasma terminating events due to excess pellet fueling and impurity injection is studied in the Large Helical Device, Wendelstein 7-X and TJ-II. Time scales for these events range from values of a decimal fraction of typical energy confinement times to the order of the energy confinement time. The leading mechanism of energy loss appears to be radiation revealing similarities to radiation collapses when a radiative density limit is approached. Differently to tokamaks, the capability of helical devices to provide magnetic confinement in vacuum (i.e. without large inductive plasma currents) gives rise to the observation of plasma recovery even after some energy confinement times. Time-scales and the dynamics of recovery for close to marginal termination indicates some robustness in the response of helical devices to large unintended perturbations.

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