Thermal energy mitigation and toroidal peaking effects in JET disruptions

ORAL  · Invited

Abstract

Thermal energy mitigation is critical to prevent damage to the tokamak in plasma disruptions. Previous investigations on JET suggest thermal stored energy (Wth) is poorly mitigated by either Massive Gas Injection (MGI) or Shattered Pellet Injection (SPI) Disruption Mitigation Systems (DMS). A contrasting investigation on ASDEX-Upgrade found that Wth is well mitigated with MGI. We investigate whether the apparent poor thermal mitigation on JET is explained by radiation peaking near the injected impurity plume, combined with the limited toroidal resolution of bolometry. High toroidal peaking in the pre-thermal quench (pre-TQ) is found in Ar/D2 MGI on JET, with >3x higher radiation near the plume than elsewhere throughout the pre-TQ. A previously unexplained toroidal peaking measurement in neon SPI is also successfully reproduced with similar peaking. These observations agree with literature from Alcator C-Mod, ASDEX-Upgrade, and KSTAR. This peaking is not captured in previous JET studies that found poor thermal mitigation. A set of 10% Ar, 90% D2 mix MGIs is analyzed using the Emis3D radiation modeling code. With injector peaking, almost two thirds of Wth is radiated, where estimates that do not account for injector peaking would indicate less than half. The toroidal spread of the injector peaking feature is poorly constrained, and up to 85% of Wth may be radiated using the largest possible spread. Similar radiated fractions are seen in a second set of MGI discharges and in a set of neon SPI discharges. The improved Wth mitigation suggests a reduced divertor melt risk in mitigated disruptions on ITER and SPARC. Higher peaking near DMS injectors could increase flash melting risk on nearby plasma facing components. Only single-injector cases are studied; simultaneous injection is not addressed.

*The JET SPI project is a collaborative effort of EURATOM, the ITER Organization, and the USDOE. It received funding from the ITER Organization.The views and opinions expressed herein do not necessarily reflect those of EUROATOM, USDOE, or the ITER Organization.This work was funded by the USDOE, FES DE-SC0014264, the ITER Organization (TA C18TD38FU), and the EUROfusion Consortium framework, Euratom research and training programme grant No 633053.

Presenters

  • Benjamin Stein-Lubrano

    • MIT PSFC

Authors

  • Benjamin Stein-Lubrano

    • MIT PSFC
  • Ryan M Sweeney

    • Commonwealth Fusion Systems
  • Jack J Lovell

    • Oak Ridge National Laboratory
  • Pedro Carvalho

    • United Kingdom Atomic Energy Authority, Culham Campus, Abingdon, UK
    • UKAEA, Culham Center for Fusion Energy
  • Larry Robert Baylor

    • ORNL
  • Robert S Granetz

    • Massachusetts Institute of Technology
  • Stefan Jachmich

    • ITER Organization, Route de Vinon-sur-Verdon - CS 90 046, 13067 St Paul Lez Durance Cedex, France
    • ITER Organization, St. Paul-lez-Durance, France
  • Emmanuel Joffrin

    • CEA-IRFM, Centre de Cadarache, Saint-Paul-lez-Durance, 13108 Cedex
    • CEA Cadarache
  • Michael Lehnen

    • ITER Organization, Route de Vinon-sur-Verdon - CS 90 046, 13067 St Paul Lez Durance Cedex, France
    • ITER Organization, St. Paul-lez-Durance, France
  • Costanza F Maggi

    • UKAEA
  • Earl S Marmar

    • MIT Plasma Science and Fusion Center
    • Massachusetts Institute of Technology MIT
  • Paulo Puglia

    • Ecole Polytechnique Federale de Lausanne
  • John Edward Rice

    • Massachusetts Institute of Technology
  • Umar Sheikh

    • EPFL, Swiss Plasma Center (SPC), CH – 1015 Lausanne, Switzerland
    • Swiss Plasma Center (SPC), École Polytechnique Fédérale de Lausanne (EPFL), Lausanne, Switzerland,
  • Daisuke Shiraki

    • Oak Ridge National Laboratory
  • Scott Silburn

    • United Kingdom Atomic Energy Authority Culham Science Centre Abingdon Oxon OX14 3DB United Kingdom of Great Britain and Northern Ireland
    • UK Atomic Energy Authority (UKAEA)