Disruption-mitigation-technology concepts and implications for ITER

L. R. Baylor, T. C. Jernigan, S. K. Combs, S. J. Meitner, J. B. Caughman, N. Commaux, D. A. Rasmussen, P. B. Parks, M. Glugla, S. Maruyama, R. J.H. Pearce, M. Lehnen

Research output: Contribution to journalArticlepeer-review

16 Scopus citations

Abstract

Disruptions on ITER present challenges to handle the intense heat flux, the large forces from halo currents, and the potential first wall damage from energetic runaway electrons. Injecting large quantities of material into the plasma during the disruption can reduce the plasma energy and increase its resistivity to mitigate these effects. Assessments of the amount of various mixtures and quantities of the material required have been made to provide collision mitigation of runaway-electron conversion, which is the most difficult challenge. The quantities of the material required (̃0.5 MPa ̇ m 3 for deuterium or helium gas) are large enough to have implications on the design and operation of the vacuum system and tokamak exhaust processing system.

Original languageEnglish
Pages (from-to)419-424
Number of pages6
JournalIEEE Transactions on Plasma Science
Volume38
Issue number3 PART 1
DOIs
StatePublished - Mar 2010

Funding

The authors would like to thank Dr. S. L. Milora for the many useful discussions and support for this work. This paper was prepared as an account of work by or for the ITER Organization. The Members of the Organization are the People’s Republic of China, the European Atomic Energy Community, the Republic of India, Japan, the Republic of Korea, the Russian Federation, and the U.S. The views and opinions expressed herein do not necessarily reflect those of the members or any agency thereof. Dissemination of the information in this paper is governed by the applicable terms of the ITER Joint Implementation Agreement. The submitted manuscript has been authored by a contractor of the U.S. Government under Contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. Manuscript received June 25, 2009; revised November 24, 2009. First published February 8, 2010; current version published March 10, 2010. This work was supported by the Oak Ridge National Laboratory managed by UT-Battelle, LLC for the U.S. Department of Energy under Contract No. DE-AC05-00OR22725 and also supported under contract DE-FC02-04ER54698. L. R. Baylor, T. C. Jernigan, S. K. Combs, S. J. Meitner, J. B. Caughman, N. Commaux, and D. A. Rasmussen are with Oak Ridge National Laboratory, Oak Ridge, TN 37831-6169 USA (e-mail: [email protected]; jernigantc@ ornl.gov; [email protected]). P. B. Parks is with General Atomics, San Diego, CA 92186-9784 USA (e-mail: [email protected]). M. Glugla, S. Maruyama, and R. J. H. Pearce are with ITER Organization, 13067 St. Paul-lez-Durance, France. M. Lehnen is with Forschungszentrum Jülich, D-52425 Jülich, Germany. Color versions of one or more of the figures in this paper are available online at http://ieeexplore.ieee.org. Digital Object Identifier 10.1109/TPS.2009.2039496

FundersFunder number
European Atomic Energy Community
U.S.
UT-Battelle
U.S. Department of EnergyDE-AC05-00OR22725, DE-FC02-04ER54698
Oak Ridge National Laboratory
Council on grants of the President of the Russian Federation

    Keywords

    • Disruption
    • ITER
    • Pellet

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