Published 2024 | Version v1
Miscellaneous Open

Thermal Energy Mitigation and Toroidal Peaking Effects in JET Disruptions

  • 1. MIT Plasma Science and Fusion Center, Cambridge, Massachusetts 01239 (United States)
  • 2. Commonwealth Fusion Systems, Devens, MA 01434 (United States)
  • 3. Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

Description

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), when measured by weighted averages of bolometer channels. A contrasting investigation on ASDEX-Upgrade found that thermal energy 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 diagnostics. High toroidal peaking in the pre-thermal quench (pre-TQ) is found in Ar/D2 MGI on JET, with > 3x higher radiation near the injection location 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 by the bolometry used 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-localized 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 the plasma's thermal energy 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 thermal mitigation found here suggests a reduced divertor melt risk in high performance mitigated disruptions on ITER and SPARC. However, the higher peaking near DMS injectors could increase flash melting risk on nearby plasma facing components. Only single-injector mitigation is studied here. Multiple injector mitigation, as planned for ITER and SPARC, might further increase the radiated fraction and decrease pre-TQ peaking, but that is not addressed in this study.

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Part of:
Third Technical Meeting on Plasma Disruptions and their Mitigation. Presentations

Additional details

Publishing Information

Imprint Title
Third Technical Meeting on Plasma Disruptions and their Mitigation. Presentations
Imprint Pagination
vp.
Journal Page Range
33 p.
Report number
INIS-XA--24M3135

Conference

Title
3. Technical Meeting on Plasma Disruptions and their Mitigation
Dates
3-6 Sep 2024
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
55090922
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALCATOR DEVICE; ASDEX TOKAMAK; BOLOMETERS; DIVERTORS; FIRST WALL; ITER TOKAMAK; PELLET INJECTION; SIMULATION; STORED ENERGY; WEIGHT
Descriptors DEC
CLOSED PLASMA DEVICES; ENERGY; MEASURING INSTRUMENTS; PHYSICAL PROPERTIES; THERMODYNAMIC PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
Imprint:Refs.