NDLI: DIII-D accomplishments and plans in support of fusion next steps

Content Provider	IEEE Xplore Digital Library
Author	Buttery, R.J. Eidietis, N. Holcomb, C. La Haye, R.J. Leonard, A. Nazikian, R. Solomon, W.M. Baylor, L. Burrell, K. Garofalo, A. Jackson, G.
Copyright Year	2013
Description	Author affiliation: Princeton Plasma Phys. Lab., Princeton, NJ, USA (Nazikian, R.; Solomon, W.M.) \|\| Gen. Atomics, San Diego, CA, USA (Buttery, R.J.; Eidietis, N.; La Haye, R.J.; Leonard, A.; Burrell, K.; Garofalo, A.; Jackson, G.) \|\| Lawrence Livermore Nat. Lab., Livermore, CA, USA (Holcomb, C.) \|\| Oak Ridge Nat. Lab., Oak Ridge, TN, USA (Baylor, L.)
Abstract	DIII-D is using its flexibility and diagnostics to address the critical science required to enable next step fusion devices. Operating scenarios for ITER have been adapted to low torque and are now being optimized for transport. Three ELM mitigation scenarios have been developed to near-ITER parameters. New control techniques are managing the most challenging plasma instabilities. Disruption mitigation tools show promising dissipation strategies for runaway electrons and heat load. An off axis neutral beam upgrade has enabled sustainment of high $β_{N}$ capable steady state regimes. Divertor research is identifying the challenge, physics and candidate solutions for handling the hot plasma exhaust with notable progress in heat flux reduction using the snowflake configuration. This work is helping optimize design choices and prepare the scientific tools for operation in ITER, and resolve key elements of the plasma configuration and divertor solution for an FNSF.
Starting Page	1
Ending Page	8
File Size	908047
Page Count	8
File Format	PDF
e-ISBN	9781479901715
DOI	10.1109/SOFE.2013.6635483
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2013-06-10
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Torque Heating Discharges (electric) Particle beams Magnetic confinement fusion tokamak plasma
Content Type	Text
Resource Type	Article

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1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
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4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
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MAST accomplishments/plans in support of fusion next-steps

EAST accomplishments/plans in support of fusion next-steps

LHD accomplishments/plans in support of fusion next-steps

Stability of negative central magnetic shear discharges in the DIII-D tokamak

Limiter bias experiments in DIII-D

Investigation of the effect of large core changes in toroidal plasma rotation and radial electric field on confinement in H-mode discharges in the DIII-D tokamak

Advanced tokamak research on the DIII-D tokamak

Confinement and stability of VH-mode discharges in the DIII-D tokamak

Enhanced confinement discharges in DIII-D with neon and argon induced radiation

DIII-D accomplishments and plans in support of fusion next steps

Similar Documents

MAST accomplishments/plans in support of fusion next-steps

EAST accomplishments/plans in support of fusion next-steps

LHD accomplishments/plans in support of fusion next-steps

Stability of negative central magnetic shear discharges in the DIII-D tokamak

Limiter bias experiments in DIII-D

Investigation of the effect of large core changes in toroidal plasma rotation and radial electric field on confinement in H-mode discharges in the DIII-D tokamak

Advanced tokamak research on the DIII-D tokamak

Confinement and stability of VH-mode discharges in the DIII-D tokamak

Enhanced confinement discharges in DIII-D with neon and argon induced radiation

DIII-D accomplishments and plans in support of fusion next steps