DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Passive deconfinement of runaway electrons using an in-vessel helical coil

Abstract

A helical coil designed to passively generate non-axisymmetric fields during a plasma disruption is shown (via electromagnetic analysis, linear MHD modeling, and relativistic drift orbit tracing) to be effective at deconfining runaway electrons (REs) on a time scale significantly faster than the plasma current quench. Magnetic equilibria from DIII-D RE-producing scenarios are used to calculate the toroidal electric field generated during the current quench phase of a disruption, which in turn drives current in the proposed n = 1 in-vessel helical coil, without the need for any external power supplies or disruption detection or prediction techniques. Simulations of the plasma evolution using the TokSys GS Evolve code predict the inductive coupling of coil currents up to 12% of the pre-disruption plasma current into the helical coil. The coil geometry is parametrically varied to maximize both the non-resonant and resonant components of the 3D magnetic perturbation, resulting in δB/B ≈ 10–2 and a vacuumisland overlapwidth of up to 0.7ψN. The REORBIT module of the MARS-F code is used to model the full non-axisymmetric magnetic field and trace RE drift orbits to determine the effect on RE deconfinement, with up to 70% of the RE orbits lost after 0.2 ms. A two-stagemore » evolution of the RE orbit loss fraction is observed to be caused by resonant trapping between multiple magnetic island chains. Finally, electromagnetic and thermal stresses on the coil are calculated to be within operational limits for installation in DIII-D, and scale favorably to a reactor-size device. Furthermore, these findings motivate future experimental study of the helical coil concept in DIII-D or other tokamaks.« less

Authors:
ORCiD logo [1]; ORCiD logo [2]; ORCiD logo [1];  [1];  [3]
  1. General Atomics, San Diego, CA (United States)
  2. General Atomics, San Diego, CA (United States); Columbia Univ., New York, NY (United States)
  3. Georgia Inst. of Technology, Atlanta, GA (United States)
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1828581
Grant/Contract Number:  
FC02-04ER54698
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 61; Journal Issue: 10; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; runaway electrons; disruption; magnetic perturbations; 3D coil

Citation Formats

Weisberg, David B., Paz-Soldan, C., Liu, Y. Q., Welander, A., and Dunn, C. Passive deconfinement of runaway electrons using an in-vessel helical coil. United States: N. p., 2021. Web. doi:10.1088/1741-4326/ac2279.
Weisberg, David B., Paz-Soldan, C., Liu, Y. Q., Welander, A., & Dunn, C. Passive deconfinement of runaway electrons using an in-vessel helical coil. United States. https://doi.org/10.1088/1741-4326/ac2279
Weisberg, David B., Paz-Soldan, C., Liu, Y. Q., Welander, A., and Dunn, C. Thu . "Passive deconfinement of runaway electrons using an in-vessel helical coil". United States. https://doi.org/10.1088/1741-4326/ac2279. https://www.osti.gov/servlets/purl/1828581.
@article{osti_1828581,
title = {Passive deconfinement of runaway electrons using an in-vessel helical coil},
author = {Weisberg, David B. and Paz-Soldan, C. and Liu, Y. Q. and Welander, A. and Dunn, C.},
abstractNote = {A helical coil designed to passively generate non-axisymmetric fields during a plasma disruption is shown (via electromagnetic analysis, linear MHD modeling, and relativistic drift orbit tracing) to be effective at deconfining runaway electrons (REs) on a time scale significantly faster than the plasma current quench. Magnetic equilibria from DIII-D RE-producing scenarios are used to calculate the toroidal electric field generated during the current quench phase of a disruption, which in turn drives current in the proposed n = 1 in-vessel helical coil, without the need for any external power supplies or disruption detection or prediction techniques. Simulations of the plasma evolution using the TokSys GS Evolve code predict the inductive coupling of coil currents up to 12% of the pre-disruption plasma current into the helical coil. The coil geometry is parametrically varied to maximize both the non-resonant and resonant components of the 3D magnetic perturbation, resulting in δB/B ≈ 10–2 and a vacuumisland overlapwidth of up to 0.7ψN. The REORBIT module of the MARS-F code is used to model the full non-axisymmetric magnetic field and trace RE drift orbits to determine the effect on RE deconfinement, with up to 70% of the RE orbits lost after 0.2 ms. A two-stage evolution of the RE orbit loss fraction is observed to be caused by resonant trapping between multiple magnetic island chains. Finally, electromagnetic and thermal stresses on the coil are calculated to be within operational limits for installation in DIII-D, and scale favorably to a reactor-size device. Furthermore, these findings motivate future experimental study of the helical coil concept in DIII-D or other tokamaks.},
doi = {10.1088/1741-4326/ac2279},
journal = {Nuclear Fusion},
number = 10,
volume = 61,
place = {United States},
year = {Thu Sep 23 00:00:00 EDT 2021},
month = {Thu Sep 23 00:00:00 EDT 2021}
}

Works referenced in this record:

Passive runaway electron suppression in tokamak disruptions
journal, July 2013

  • Smith, H. M.; Boozer, A. H.; Helander, P.
  • Physics of Plasmas, Vol. 20, Issue 7
  • DOI: 10.1063/1.4813255

Simulation of runaway electrons, transport affected by J-TEXT resonant magnetic perturbation
journal, July 2016


Analysis of the direction of plasma vertical movement during major disruptions in ITER
journal, October 2005

  • Lukash, Victor; Sugihara, Masayoshi; Gribov, Yuri
  • Plasma Physics and Controlled Fusion, Vol. 47, Issue 12
  • DOI: 10.1088/0741-3335/47/12/001

A design retrospective of the DIII-D tokamak
journal, May 2002


Modelling intrinsic error field correction experiments in MAST
journal, August 2014


Kink instabilities of the post-disruption runaway electron beam at low safety factor
journal, March 2019

  • Paz-Soldan, C.; Eidietis, N. W.; Liu, Y. Q.
  • Plasma Physics and Controlled Fusion, Vol. 61, Issue 5
  • DOI: 10.1088/1361-6587/aafd15

Separation of β̄ p and ℓ i in tokamaks of non-circular cross-section
journal, October 1985


Study of in-vessel nonaxisymmetric ELM suppression coil concepts for ITER
journal, January 2008


MARS-F modeling of post-disruption runaway beam loss by magnetohydrodynamic instabilities in DIII-D
journal, October 2019


Runaway electron losses caused by resonant magnetic perturbations in ITER
journal, July 2011


The advanced tokamak path to a compact net electric fusion pilot plant
journal, March 2021


Feedback stabilization of nonaxisymmetric resistive wall modes in tokamaks. I. Electromagnetic model
journal, September 2000

  • Liu, Y. Q.; Bondeson, A.; Fransson, C. M.
  • Physics of Plasmas, Vol. 7, Issue 9
  • DOI: 10.1063/1.1287744

Development of ITER-relevant plasma control solutions at DIII-D
journal, July 2007


Two beneficial non-axisymmetric perturbations to tokamaks
journal, May 2011


Runaway electron experiments at COMPASS in support of the EUROfusion ITER physics research
journal, November 2018

  • Mlynar, J.; Ficker, O.; Macusova, E.
  • Plasma Physics and Controlled Fusion, Vol. 61, Issue 1
  • DOI: 10.1088/1361-6587/aae04a

Dissipation of post-disruption runaway electron plateaus by shattered pellet injection in DIII-D
journal, March 2018