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Development and experimental qualification of novel disruption prevention techniques on DIII-D

Journal Article · · Nuclear Fusion
 [1];  [2];  [2];  [2];  [2];  [3];  [2];  [4];  [2];  [3];  [2];  [5];  [6];  [2];  [2];  [4]
  1. General Atomics, San Diego, CA (United States); General Atomics
  2. General Atomics, San Diego, CA (United States)
  3. Massachusetts Inst. of Technology Plasma Science and Fusion Center, Cambridge, MA (United States)
  4. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  5. Dalian Univ. of Technology (China)
  6. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Novel disruption prevention solutions spanning a range of control regimes are being developed and tested on DIII-D to enable ITER success. First, a new real-time control algorithm has been developed and tested for regulating nearness to stability limits and maintaining safety-margins. Its first application has been for reliable prevention of vertical displacement events (VDEs) by adjusting plasma elongation (κ) and the inner-gap between the plasma and inner-wall in response to real- time open-loop VDE growth rate (γ) estimators. VDEs were robustly prevented up to average open-loop growth rates of 800 rad/s with initial tunings, with only applying shape modification when near safety limits. Second, the disruption risk during fast, emergency shutdown after large tearing and locked modes can be significantly improved by transitioning to a limited topology during shutdown. More than 50% of emergency limited shutdowns after locked modes reach a final normalized current I_N < 0.3 before terminating, scaling to the 3 MA ITER requirement. Furthermore, this is in contrast to diverted shutdowns, the majority of which disrupt at I_N > 0.8. Despite improvements, these results highlight the critical importance of early prevention. Third, a novel emergency shut down method has been developed which excites instabilities to form a warm, helical core post-thermal quench. The current quench extends to ~100ms and avoids VDEs and runaway electron generation. Novel real-time machine learning disruption prediction has been integrated with the DIII-D proximity controller, and a real- time compatible multi-mode MHD spectroscopy technique has been developed. Results presented here were enabled by a focused effort, the Disruption Free Protocol, in DIII-D’s 2019-20 campaign to complement disruption prevention experiments with a large piggy-back program. In addition to testing novel techniques, it is estimated to have helped avoid 32 potential disruptions in piggyback operations with rapid, early shutdowns after large rotating n=1 or locked modes.

Research Organization:
General Atomics, San Diego, CA (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
FC02-04ER54698; AC02-09CH11466; AC52-07NA27344; SC0014264
OSTI ID:
1826166
Alternate ID(s):
OSTI ID: 1836940
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 12 Vol. 61; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (15)

Event detection and exception handling strategies in the ASDEX Upgrade discharge control system journal October 2013
Avoidance of vertical displacement events in DIII-D using a neural network growth rate estimator journal August 2021
The influence of an ITER-like wall on disruptions at JET journal May 2014
Real time equilibrium reconstruction for tokamak discharge control journal July 1998
Experimental vertical stability studies for ITER performance and design guidance journal September 2009
Statistical analysis of disruptions in JET journal April 2009
Survey of disruption causes at JET journal April 2011
Feedback control of the proximity to marginal RWM stability using active MHD spectroscopy journal November 2011
Path-oriented early reaction to approaching disruptions in ASDEX Upgrade and TCV in view of the future needs for ITER and DEMO journal November 2017
Tests of the real-time vertical growth rate calculation on EAST journal June 2020
Multi-machine analysis of termination scenarios with comparison to simulations of controlled shutdown of ITER discharges journal December 2017
Implementing a finite-state off-normal and fault response system for disruption avoidance in tokamaks journal March 2018
A real-time machine learning-based disruption predictor in DIII-D journal July 2019
First observation of plasma healing via helical equilibrium in tokamak disruptions journal July 2019
Identification of multiple eigenmode growth rates towards real time detection in DIII-D and KSTAR tokamak plasmas journal April 2021

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