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Title: Injection of multiple shattered pellets for disruption mitigation in DIII-D

Conference ·

Plasma shutdown experiments in DIII-D have injected multiple shattered pellets at different toroidal locations for the first time, as is planned for the ITER disruption mitigation system. Systematically varying the relative timing of the two pellets suggests that simultaneously injected pellets may influence the assimilation of each other, altering the resulting disruption characteristics compared to a single pellet injecting similar neon quantities. Thermal quench (TQ) radiation measured near the injection location is reduced with the dual pellets, contrary to TQ radiation measured away from the injection ports, which does not show a clear difference between single or dual pellet injections. The mitigation of other disruption loads, such as the current quench (CQ) duration and divertor heat loads, decrease when the pellets enter the plasma simultaneously compared to single shattered pellet injections with similar neon quantities. This similar reduction in mitigation of CQ and conductive loads is consistent with the observed reduction in total TQ radiation. The time between initial pellet injection and the end of the TQ is shorter when both pellets are injected simultaneously compared to a single pellet. This lower cooling duration may limit the amount of the neon assimilated by the plasma prior to the end of the TQ, consistent with the observed reduction in radiation. The injected impurities spread primarily in the parallel direction, away from the source at the injection location. The addition of two shattered pellet injectors shows that the initial poloidal radiation is spread out into two distinct regions, cooling multiple flux tubes simultaneously, which may induce global MHD instabilities more rapidly than a single flux tube of impurities leading to a shorter cooling duration. The electron density increased by approximately a factor of two with the addition of multiple pellets, but is highly sensitive to the time between injections. A maximum density increase is found when both pellets arrive at the plasma prior to the start of the TQ.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1560440
Resource Relation:
Journal Volume: 59; Journal Issue: 10; Conference: IAEA Fusion Energy Conference (FEC 2018) - Ahmedabad, , India - 10/22/2018 7:00:00 AM-10/27/2018 7:00:00 AM
Country of Publication:
United States
Language:
English

References (23)

Soft x-ray array system with variable filters for the DIII-D tokamak journal November 2011
Poloidal radiation asymmetries during disruption mitigation by massive gas injection on the DIII-D tokamak journal October 2017
Equilibrium analysis of current profiles in tokamaks journal June 1990
Chapter 3: MHD stability, operational limits and disruptions journal December 1999
Wide-angle ITER-prototype tangential infrared and visible viewing system for DIII-D journal November 2014
The role of MHD in 3D aspects of massive gas injection journal June 2015
Mitigation of upward and downward vertical displacement event heat loads with upper or lower massive gas injection in DIII-D journal October 2015
Thermal quench mitigation and current quench control by injection of mixed species shattered pellets in DIII-D journal June 2016
Time resolved radiated power during tokamak disruptions and spectral averaging of AXUV photodiode response in DIII-D journal February 2004
Disruptions in ITER and strategies for their control and mitigation journal August 2015
Alternative Techniques for Injecting Massive Quantities of Gas for Plasma-Disruption Mitigation journal March 2010
Design and Commissioning of a Three-Barrel Shattered Pellet Injector for DIII-D Disruption Mitigation Studies journal June 2017
Disruption Mitigation System Developments and Design for ITER journal September 2015
First demonstration of rapid shutdown using neon shattered pellet injection for thermal quench mitigation on DIII-D journal March 2016
Radiation asymmetries during disruptions on DIII-D caused by massive gas injectiona) journal October 2014
Plasma radiometry with 30 chord resolution for fast transients in the DIII-D tokamak journal October 2004
Modeling of stochastic magnetic flux loss from the edge of a poloidally diverted tokamak journal December 2002
Imaging divertor strike point splitting in RMP ELM suppression experiments in the DIII-D tokamak journal October 2018
Real‐time, vibration‐compensated CO 2 interferometer operation on the DIII‐D tokamak journal July 1988
Chapter 3: MHD stability, operational limits and disruptions journal June 2007
Chapter 3: MHD stability, operational limits and disruptions journal June 2007
Disruption Mitigation System Developments and Design for ITER journal September 2015
Alternative Techniques for Injecting Massive Quantities of Gas for Plasma-Disruption Mitigation journal March 2010

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