Density and temperature profiles after low-Z and high-Z shattered pellet injections on DIII-D
Abstract
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. 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 thermal quench, 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 furthermore »
- Publication Date:
- Research Org.:
- General Atomics, San Diego, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF)
- OSTI Identifier:
- 2208851
- Alternate Identifier(s):
- OSTI ID: 2204518; OSTI ID: 2204714; OSTI ID: 2281096
- Grant/Contract Number:
- AC05-00OR22725; FC02-04ER54698; FG02-07ER54917
- Resource Type:
- Published Article
- Journal Name:
- Nuclear Fusion
- Additional Journal Information:
- Journal Name: Nuclear Fusion Journal Volume: 64 Journal Issue: 1; Journal ID: ISSN 0029-5515
- Publisher:
- IOP Publishing
- Country of Publication:
- IAEA
- Language:
- English
- Subject:
- shattered pellet injection; staggered injection; disruption mitigation; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Citation Formats
Lvovskiy, A., Matsuyama, A., O’Gorman, T., Shiraki, D., Herfindal, J. L., Hollmann, E. M., Marini, C., Boivin, R., Eidietis, N. W., and Lehnen, M. Density and temperature profiles after low-Z and high-Z shattered pellet injections on DIII-D. IAEA: N. p., 2023.
Web. doi:10.1088/1741-4326/ad0905.
Lvovskiy, A., Matsuyama, A., O’Gorman, T., Shiraki, D., Herfindal, J. L., Hollmann, E. M., Marini, C., Boivin, R., Eidietis, N. W., & Lehnen, M. Density and temperature profiles after low-Z and high-Z shattered pellet injections on DIII-D. IAEA. https://doi.org/10.1088/1741-4326/ad0905
Lvovskiy, A., Matsuyama, A., O’Gorman, T., Shiraki, D., Herfindal, J. L., Hollmann, E. M., Marini, C., Boivin, R., Eidietis, N. W., and Lehnen, M. Tue .
"Density and temperature profiles after low-Z and high-Z shattered pellet injections on DIII-D". IAEA. https://doi.org/10.1088/1741-4326/ad0905.
@article{osti_2208851,
title = {Density and temperature profiles after low-Z and high-Z shattered pellet injections on DIII-D},
author = {Lvovskiy, A. and Matsuyama, A. and O’Gorman, T. and Shiraki, D. and Herfindal, J. L. and Hollmann, E. M. and Marini, C. and Boivin, R. and Eidietis, N. W. and Lehnen, M.},
abstractNote = {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. 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 thermal quench, 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.},
doi = {10.1088/1741-4326/ad0905},
journal = {Nuclear Fusion},
number = 1,
volume = 64,
place = {IAEA},
year = {Tue Nov 14 00:00:00 EST 2023},
month = {Tue Nov 14 00:00:00 EST 2023}
}
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