Comparison of different noble gas injections by massive gas injection on plasma disruption mitigation on Experimental Advanced Superconducting Tokamak
SB Zhao, HD Zhuang, JS Yuan, DH Zhang… - Chinese …, 2023 - iopscience.iop.org
Massive gas injection (MGI) is a traditional plasma disruption mitigation method. This
method directly injected massive gas into the pre-disruption plasma and had been …
method directly injected massive gas into the pre-disruption plasma and had been …
First results on disruption mitigation by massive gas injection in Korea Superconducting Tokamak Advanced Research
Y Yu, YO Kim, HK Kim, HT Kim, WC Kim… - Review of Scientific …, 2012 - pubs.aip.org
Massive gas injection (MGI) system was developed on Korea Superconducting Tokamak
Advanced Research (KSTAR) in 2011 campaign for disruption studies. The MGI valve has a …
Advanced Research (KSTAR) in 2011 campaign for disruption studies. The MGI valve has a …
Development of a Fast Valve for Disruption Mitigation and its Preliminary Application to EAST and HT-7
H Zhuang, X Zhang - Plasma Science and Technology, 2013 - iopscience.iop.org
In large tokamaks, disruption of high current plasma would damage plasma facing
component surfaces (PFCs) or other inner components due to high heat load …
component surfaces (PFCs) or other inner components due to high heat load …
First results of Ne shattered pellet injection for mitigating plasma disruption with full metal wall in EAST tokamak
JS Yuan, GZ Zuo, SB Zhao, L Li, HD Zhuang… - Nuclear …, 2023 - iopscience.iop.org
Disruption mitigation poses a significant and unresolved challenge for ITER and future
fusion reactor devices. To mitigate the effect of plasma disruption, a Shattered Pellet …
fusion reactor devices. To mitigate the effect of plasma disruption, a Shattered Pellet …
Runaway current suppression by secondary massive gas injection during the disruption mitigation phase on J-TEXT
YN Wei, W Yan, ZY Chen, RH Tong… - Plasma Physics and …, 2019 - iopscience.iop.org
Disruption is one of the urgent problems for future tokamaks in possibly causing heat loads,
halo currents, and runaway electrons (REs). Massive impurity injection is a feasible way to …
halo currents, and runaway electrons (REs). Massive impurity injection is a feasible way to …
Effects of helium massive gas injection level on disruption mitigation on EAST
In this study, NIMROD simulations are performed to investigate the effects of massive helium
gas injection level on the induced disruption on EAST tokamak. It is demonstrated in …
gas injection level on the induced disruption on EAST tokamak. It is demonstrated in …
Experimental study of disruption mitigation using massive injection of noble gases on Tore Supra
C Reux, J Bucalossi, F Saint-Laurent, C Gil… - Nuclear …, 2010 - iopscience.iop.org
Disruptions are a major threat for future tokamaks, including ITER. Disruption-generated
heat loads, electromagnetic forces and runaway electrons will not be tolerable for next …
heat loads, electromagnetic forces and runaway electrons will not be tolerable for next …
Measurements of impurity mixing efficiency during massive gas injection in J-TEXT
W Li, RH Tong, W Bai, DW Huang, W Yan… - Plasma Physics and …, 2020 - iopscience.iop.org
Experiments of disruption mitigation with massive gas injection have been conducted in J-
TEXT tokamak with various impurities (He, Ne, Ar and He&Ar (90%: 10%) mixtures) …
TEXT tokamak with various impurities (He, Ne, Ar and He&Ar (90%: 10%) mixtures) …
[PDF][PDF] Mitigation of runaway current with supersonic molecular beam injection on HL-2A tokamak
Y Liu, Y Dong, X Peng, C Chen, Y Zhang… - 26th IAEA Fusion …, 2016 - nucleus.iaea.org
Disruptions are a major threat for future reactor-size tokamaks, its damage can come from
overheating of divertor surfaces, electromagnetic loads on conducing structures, and …
overheating of divertor surfaces, electromagnetic loads on conducing structures, and …
DIII-D studies of massive gas injection fast shutdowns for disruption mitigation
Injection of massive quantities of gas is a promising technique for fast shutdown of ITER for
the purpose of avoiding divertor and first wall damage from disruptions. Previous …
the purpose of avoiding divertor and first wall damage from disruptions. Previous …
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