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

Buttery, R. J; Eidietis, N.; Holcomb, C.; Haye, R. J. La; Leonard, A.; Nazikian, R.; Solomon, W. M.; Baylor, L.; Burrell, K; Garofalo, A.; Jackson, G.

doi:10.1109/SOFE.2013.6635483

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

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Abstract

DIII-D is using its flexibility and diagnostics to address the critical science required to enable next step fusion devices. We have adapted operating scenarios for ITER 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 βN 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. Our 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.

Authors:

Buttery, R. J ^[1]; Eidietis, N. ^[1]; Holcomb, C. ^[2]; Haye, R. J. La ^[1]; Leonard, A. ^[1]; Nazikian, R. ^[3]; Solomon, W. M. ^[3]; Baylor, L. ^[4]; Burrell, K ^[1]; Garofalo, A. ^[1]; Jackson, G. ^[1]

General Atomics, San Diego, CA (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: Sat Jun 01 00:00:00 EDT 2013

Research Org.:: General Atomics, San Diego, CA (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

Contributing Org.:: DIII-D Team

OSTI Identifier:: 1345493

Grant/Contract Number:: FC02-04ER54698; AC52-07NA27344; AC02-09CH11466

Resource Type:: Accepted Manuscript

Journal Name:: IEEE Transactions on Plasma Science

Additional Journal Information:: Journal Volume: 2013; Journal ID: ISSN 0093-3813

Publisher:: IEEE

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; tokamak; plasma; fusion

Citation Formats


                    Buttery, R. J, Eidietis, N., Holcomb, C., Haye, R. J. La, Leonard, A., Nazikian, R., Solomon, W. M., Baylor, L., Burrell, K, Garofalo, A., and Jackson, G. DIII-D accomplishments and plans in support of fusion next steps.  United States: N. p., 2013. 
Web.  doi:10.1109/SOFE.2013.6635483.

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                    Buttery, R. J, Eidietis, N., Holcomb, C., Haye, R. J. La, Leonard, A., Nazikian, R., Solomon, W. M., Baylor, L., Burrell, K, Garofalo, A., & Jackson, G. DIII-D accomplishments and plans in support of fusion next steps.  United States.  https://doi.org/10.1109/SOFE.2013.6635483

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                    Buttery, R. J, Eidietis, N., Holcomb, C., Haye, R. J. La, Leonard, A., Nazikian, R., Solomon, W. M., Baylor, L., Burrell, K, Garofalo, A., and Jackson, G. Sat .  
"DIII-D accomplishments and plans in support of fusion next steps".  United States.  https://doi.org/10.1109/SOFE.2013.6635483.  https://www.osti.gov/servlets/purl/1345493.

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@article{osti_1345493,

  title        = {DIII-D accomplishments and plans in support of fusion next steps},

  author       = {Buttery, R. J and Eidietis, N. and Holcomb, C. and Haye, R. J. La and Leonard, A. and Nazikian, R. and Solomon, W. M. and Baylor, L. and Burrell, K and Garofalo, A. and Jackson, G.},

  abstractNote = {DIII-D is using its flexibility and diagnostics to address the critical science required to enable next step fusion devices. We have adapted operating scenarios for ITER 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 βN 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. Our 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.},

  doi          = {10.1109/SOFE.2013.6635483},

  journal      = {IEEE Transactions on Plasma Science},

  number       = ,

  volume       = 2013,

  place        = {United States},

  year         = {Sat Jun 01 00:00:00 EDT 2013},

  month        = {Sat Jun 01 00:00:00 EDT 2013}

}

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