MIT Libraries logoDSpace@MIT

MIT
View Item 
  • DSpace@MIT Home
  • MIT Open Access Articles
  • MIT Open Access Articles
  • View Item
  • DSpace@MIT Home
  • MIT Open Access Articles
  • MIT Open Access Articles
  • View Item
JavaScript is disabled for your browser. Some features of this site may not work without it.

Gas jet disruption mitigation studies on Alcator C-Mod and DIII-D

Author(s)
Hollmann, E. M.; Whyte, D. G.; Antar, G. Y.; Bakhtiari, M.; Boedo, J. A.; Evans, T. E.; Jernigan, T. C.; Gray, D. S.; Groth, M.; Humphreys, D. A.; Lasnier, C. J.; Moyer, R. A.; Parks, P. B; Rudakov, D. L.; Strait, E. J.; Wesley, J.; West, W. P.; Wurden, G.; Yu, J.; Granetz, Robert S.; Izzo, Viviana A.; Bader, Aaron Craig; Biewer, T.; Hutchinson, Ian H.; Reinke, Matthew Logan; Terry, James L; Hutchinson, Ian Horner; ... Show more Show less
Thumbnail
DownloadGranetz_Nuc_Fus.pdf (960.1Kb)
PUBLISHER_POLICY

Publisher Policy

Article is made available in accordance with the publisher's policy and may be subject to US copyright law. Please refer to the publisher's site for terms of use.

Terms of use
Article is made available in accordance with the publisher's policy and may be subject to US copyright law. Please refer to the publisher's site for terms of use.
Metadata
Show full item record
Abstract
High-pressure noble gas jet injection is a mitigation technique which potentially satisfies the requirements of fast response time and reliability, without degrading subsequent discharges. Previously reported gas jet experiments on DIII-D showed good success at reducing deleterious disruption effects. In this paper, results of recent gas jet disruption mitigation experiments on Alcator C-Mod and DIII-D are reported. Jointly, these experiments have greatly improved the understanding of gas jet dynamics and the processes involved in mitigating disruption effects. In both machines, the sequence of events following gas injection is observed to be quite similar: the jet neutrals stop near the plasma edge, the edge temperature collapses and large MHD modes are quickly destabilized, mixing the hot plasma core with the edge impurity ions and radiating away the plasma thermal energy. High radiated power fractions are achieved, thus reducing the conducted heat loads to the chamber walls and divertor. A significant (2 × or more) reduction in halo current is also observed. Runaway electron generation is small or absent. These similar results in two quite different tokamaks are encouraging for the applicability of this disruption mitigation technique to ITER.
Date issued
2007-08
URI
http://hdl.handle.net/1721.1/55962
Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering; Massachusetts Institute of Technology. Plasma Science and Fusion Center
Journal
Nuclear Fusion
Publisher
Institute of Physics Publishing
Citation
R.S. Granetz et al 2007 Nucl. Fusion 47 1086 doi: 10.1088/0029-5515/47/9/003 © IOP Publishing 2007
Version: Author's final manuscript
ISSN
0029-5515
1741-4326

Collections
  • MIT Open Access Articles

Browse

All of DSpaceCommunities & CollectionsBy Issue DateAuthorsTitlesSubjectsThis CollectionBy Issue DateAuthorsTitlesSubjects

My Account

Login

Statistics

OA StatisticsStatistics by CountryStatistics by Department
MIT Libraries
PrivacyPermissionsAccessibilityContact us
MIT
Content created by the MIT Libraries, CC BY-NC unless otherwise noted. Notify us about copyright concerns.