Density and temperature profiles after low-Z and high-Z shattered pellet injections on DIII-D

被引:2
|
作者
Lvovskiy, A. [1 ]
Matsuyama, A. [2 ]
O'Gorman, T. [1 ]
Shiraki, D. [3 ]
Herfindal, J. L. [3 ]
Hollmann, E. M. [4 ]
Marini, C. [4 ]
Boivin, R. [1 ]
Lehnen, M. [5 ]
Eidietis, N. W. [1 ]
机构
[1] Gen Atom, San Diego, CA 92127 USA
[2] Natl Inst Quantum Sci & Technol, Chiba, Japan
[3] Oak Ridge Natl Lab, Oak Ridge, TN USA
[4] Univ Calif San Diego, La Jolla, CA USA
[5] ITER Org, St Paul Les Durance, France
关键词
shattered pellet injection; staggered injection; disruption mitigation; DISRUPTION MITIGATION; CLOUD;
D O I
10.1088/1741-4326/ad0905
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
In this work we utilize the recently upgraded Thomson scattering diagnostic to resolve density and temperature plasma profiles after pure deuterium and mixed neon/deuterium shattered pellet injections (SPIs) on DIII-D. This allows us to study individual components of the staggered scheme proposed for disruption mitigation on ITER, consisting of a low-Z material SPI followed by a delayed high-Z SPI. Obtained spatio-temporal density profiles exhibit very different dynamics after dominantly neon and pure deuterium SPIs. The neon SPI causes a fast radiative plasma collapse in a few milliseconds and results in almost flat density profile once the impurity mixes with the plasma during and after the thermal quench (TQ). The deuterium SPI leads to a disruption delayed by ten and more milliseconds, but very limited core fueling can be observed before the disruption. Even during and after the TQ, the edge deuterium density significantly exceeds the core density. 1D transport modeling suggests that this poor core fueling can be explained by strong outward grad-B-induced drift of the injected deuterium. Preliminary simulations show that larger pellet shards and greater injected quantity can be used to improve the penetration of the low-Z material into the core. These results call for optimization and further evaluation of the staggered SPI on ITER.
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页数:10
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