E×B flux driven detachment bifurcation in the DIII-D tokamak
A bifurcative step transition from low-density, high-temperature, attached divertor conditions to high-density, low-temperature, detached divertor conditions is experimentally observed in DIII-D tokamak plasmas as density is increased. The step transition is only observed in the high confinement mod...
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| Vydané v: | Physical review letters Ročník 121; číslo 7; s. 075001 |
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| Hlavní autori: | , , , , , , , , , , , |
| Médium: | Journal Article |
| Jazyk: | English |
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United States
American Physical Society
17.08.2018
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| ISSN: | 0031-9007, 1079-7114, 1079-7114 |
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| Abstract | A bifurcative step transition from low-density, high-temperature, attached divertor conditions to high-density, low-temperature, detached divertor conditions is experimentally observed in DIII-D tokamak plasmas as density is increased. The step transition is only observed in the high confinement mode and only when the B×∇B drift is directed towards the divertor. This work reports for the first time a theoretical explanation and numerical simulations that qualitatively reproduce this bifurcation and its dependence on the toroidal field direction. According to the model, the bifurcation is primarily driven by the interdependence of the E×B-drift fluxes, divertor electric potential structure, and divertor conditions. In the attached conditions, strong potential gradients in the low field side (LFS) divertor drive E×B-drift flux towards the high field side divertor, reinforcing low density, high temperature conditions in the LFS divertor leg. At the onset of detachment, reduction in the potential gradients in the LFS divertor leg reduce the E×B-drift flux as well, such that the divertor plasma evolves nonlinearly to high density, strongly detached conditions. Experimental estimates of the E×B-drift fluxes, based on divertor Thomson scattering measurements, and their dependence on the divertor conditions are qualitatively consistent with the numerical predictions. The implications for divertor power exhaust and detachment control in the next step fusion devices are discussed. |
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| AbstractList | A bifurcative step transition from low-density, high-temperature, attached divertor conditions to high-density, low-temperature, detached divertor conditions is experimentally observed in DIII-D tokamak plasmas as density is increased. The step transition is only observed in the high confinement mode and only when the B×∇B drift is directed towards the divertor. This work reports for the first time a theoretical explanation and numerical simulations that qualitatively reproduce this bifurcation and its dependence on the toroidal field direction. According to the model, the bifurcation is primarily driven by the interdependence of the E×B-drift fluxes, divertor electric potential structure, and divertor conditions. In the attached conditions, strong potential gradients in the low field side (LFS) divertor drive E×B-drift flux towards the high field side divertor, reinforcing low density, high temperature conditions in the LFS divertor leg. At the onset of detachment, reduction in the potential gradients in the LFS divertor leg reduce the E×B-drift flux as well, such that the divertor plasma evolves nonlinearly to high density, strongly detached conditions. Experimental estimates of the E×B-drift fluxes, based on divertor Thomson scattering measurements, and their dependence on the divertor conditions are qualitatively consistent with the numerical predictions. The implications for divertor power exhaust and detachment control in the next step fusion devices are discussed. A bifurcative step transition from low-density, high-temperature, attached divertor conditions to high-density, low-temperature, detached divertor conditions is experimentally observed in DIII-D tokamak plasmas as density is increased. The step transition is only observed in the high confinement mode and only when the B×∇B drift is directed towards the divertor. This work reports for the first time a theoretical explanation and numerical simulations that qualitatively reproduce this bifurcation and its dependence on the toroidal field direction. According to the model, the bifurcation is primarily driven by the interdependence of the E×B-drift fluxes, divertor electric potential structure, and divertor conditions. In the attached conditions, strong potential gradients in the low field side (LFS) divertor drive E×B-drift flux towards the high field side divertor, reinforcing low density, high temperature conditions in the LFS divertor leg. At the onset of detachment, reduction in the potential gradients in the LFS divertor leg reduce the E×B-drift flux as well, such that the divertor plasma evolves nonlinearly to high density, strongly detached conditions. Experimental estimates of the E×B-drift fluxes, based on divertor Thomson scattering measurements, and their dependence on the divertor conditions are qualitatively consistent with the numerical predictions. The implications for divertor power exhaust and detachment control in the next step fusion devices are discussed.A bifurcative step transition from low-density, high-temperature, attached divertor conditions to high-density, low-temperature, detached divertor conditions is experimentally observed in DIII-D tokamak plasmas as density is increased. The step transition is only observed in the high confinement mode and only when the B×∇B drift is directed towards the divertor. This work reports for the first time a theoretical explanation and numerical simulations that qualitatively reproduce this bifurcation and its dependence on the toroidal field direction. According to the model, the bifurcation is primarily driven by the interdependence of the E×B-drift fluxes, divertor electric potential structure, and divertor conditions. In the attached conditions, strong potential gradients in the low field side (LFS) divertor drive E×B-drift flux towards the high field side divertor, reinforcing low density, high temperature conditions in the LFS divertor leg. At the onset of detachment, reduction in the potential gradients in the LFS divertor leg reduce the E×B-drift flux as well, such that the divertor plasma evolves nonlinearly to high density, strongly detached conditions. Experimental estimates of the E×B-drift fluxes, based on divertor Thomson scattering measurements, and their dependence on the divertor conditions are qualitatively consistent with the numerical predictions. The implications for divertor power exhaust and detachment control in the next step fusion devices are discussed. |
| ArticleNumber | 075001 |
| Author | Hill, D. N. Leonard, A. W. Samuell, C. M. Jaervinen, A. E. Eldon, D. Wang, H. Q. Fenstermacher, M. E. Groth, M. Porter, G. D. McLean, A. G. Allen, S. L. Rognlien, T. D. |
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| BackLink | https://www.ncbi.nlm.nih.gov/pubmed/30169054$$D View this record in MEDLINE/PubMed https://www.osti.gov/biblio/1464582$$D View this record in Osti.gov |
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| References | PhysRevLett.121.075001Cc20R1 PhysRevLett.121.075001Cc10R1 PhysRevLett.121.075001Cc11R1 PhysRevLett.121.075001Cc12R1 PhysRevLett.121.075001Cc13R1 PhysRevLett.121.075001Cc14R1 PhysRevLett.121.075001Cc24R1 PhysRevLett.121.075001Cc15R1 PhysRevLett.121.075001Cc16R1 PhysRevLett.121.075001Cc17R1 S. I. Braginskii (PhysRevLett.121.075001Cc23R1) 1965 PhysRevLett.121.075001Cc18R1 PhysRevLett.121.075001Cc8R1 PhysRevLett.121.075001Cc19R1 PhysRevLett.121.075001Cc9R1 P. C. Stangeby (PhysRevLett.121.075001Cc22R1) 2000 PhysRevLett.121.075001Cc6R1 PhysRevLett.121.075001Cc7R1 PhysRevLett.121.075001Cc3R1 PhysRevLett.121.075001Cc4R1 PhysRevLett.121.075001Cc2R1 PhysRevLett.121.075001Cc5R1 PhysRevLett.121.075001Cc1R1 |
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| SubjectTerms | Bifurcation theory Computer simulation Density Dependence Detaching Drift Fluxes Mathematical models Plasmas Potential gradient Thomson scattering Tokamak devices |
| Title | E×B flux driven detachment bifurcation in the DIII-D tokamak |
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