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

Full Record
Other Related Research

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:: 2013-06-01

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.

Copy to clipboard


                    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

Copy to clipboard


                    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.

Copy to clipboard


                    
@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         = {2013},

  month        = {6}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1109/SOFE.2013.6635483

Other availability

Search WorldCat to find libraries that may hold this journal

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

DIII-D research towards resolving key issues for ITER and steady-state tokamaks

Journal Article Hill, D. N. - Nuclear Fusion

The DIII-D research program is addressing key ITER research needs and developing the physics basis for future steady-state tokamaks. Pellet pacing edge-localized mode (ELM) control in the ITER configuration reduces ELM energy loss in proportion to 1/f_pellet by inducing ELMs at up to 12× the natural ELM rate. Complete suppression of ELMs with resonant magnetic perturbations has been extended to the q₉₅ expected for ITER baseline scenario discharges, and long-duration ELM-free QH-mode discharges have been produced with ITER-relevant co-current neutral-beam injection (NBI) using external n = 3 coils to generate sufficient counter-I_p torque. ITER baseline discharges at β_N ~ 2 and scaled NBI torque have been maintained in stationary conditions for more than four resistive times using electron cyclotron current drive (ECCD) for tearing mode suppression and disruption avoidance; active tracking with steerable launchers and feedback control catch these modes at small amplitude, reducing the ECCD power required to suppress them. Massive high-Z gas injection into disruption-induced 300–600 kA 20MeV runaway electron (RE) beams yield dissipation rates ~10more »« less
https://doi.org/10.1088/0029-5515/53/10/104001

Full Text Available
DIII-D research to address key challenges for ITER and fusion energy

Journal Article Buttery, Richard J. - Nuclear Fusion

DIII-D has made significant advances in the scientific basis for fusion energy. The physics mechanism of resonant magnetic perturbation (RMP) edge localized mode (ELM) suppression is revealed as field penetration at the pedestal top, and reduced coil set operation was demonstrated. Disruption runaway electrons were effectively quenched by shattered pellets; runaway dissipation is explained by pitch angle scattering. Modest thermal quench radiation asymmetries are well described NIMROD modeling. With good pedestal regulation and error field correction, low torque ITER baselines have been demonstrated and shown to be compatible with an ITER test blanket module simulator. However performance and long wavelengthmore »« less
Cited by 12
https://doi.org/10.1088/0029-5515/55/10/104017

Full Text Available
DIII-D research advancing the physics basis for optimizing the tokamak approach to fusion energy

Journal Article Fenstermacher, M. E. ; Abbate, J. ; Abe, S. ; ... - Nuclear Fusion

DIII-D physics research addresses critical challenges for the operation of ITER and the next generation of fusion energy devices. This is done through a focus on innovations to provide solutions for high performance long pulse operation, coupled with fundamental plasma physics understanding and model validation, to drive scenario development by integrating high performance core and boundary plasmas. Substantial increases in off-axis current drive efficiency from an innovative top launch system for EC power, and in pressure broadening for Alfven eigenmode control from a co-/counter-I_p steerable off-axis neutral beam, all improve the prospects for optimization of future long pulse/steady state highmore »« less
https://doi.org/10.1088/1741-4326/ac2ff2

Full Text Available
Developing and validating advanced divertor solutions on DIII-D for next-step fusion devices

Journal Article Guo, H. Y. ; Hill, D. N. ; Leonard, A. W. ; ... - Nuclear Fusion

A major challenge facing the design and operation of next-step high-power steady-state fusion devices is to develop a viable divertor solution with order-of-magnitude increases in power handling capability relative to present experience, while having acceptable divertor target plate erosion and being compatible with maintaining good core plasma confinement. A new initiative has been launched on DIII-D to develop the scientific basis for design, installation, and operation of an advanced divertor to evaluate boundary plasma solutions applicable to next step fusion experiments beyond ITER. Developing the scientific basis for fusion reactor divertor solutions must necessarily follow three lines of research, whichmore »« less
Cited by 20
https://doi.org/10.1088/0029-5515/56/12/126010

Full Text Available
DIII-D research towards establishing the scientific basis for future fusion reactors

Journal Article Petty, C. C. - Nuclear Fusion

DIII-D research is addressing critical challenges in preparation for ITER and the next generation of fusion devices through focusing on plasma physics fundamentals that underpin key fusion goals, understanding the interaction of disparate core and boundary plasma physics, and developing integrated scenarios for achieving high performance fusion regimes. Fundamental investigations into fusion energy science find that anomalous dissipation of runaway electrons (RE) that arise following a disruption is likely due to interactions with RE-driven kinetic instabilities, some of which have been directly observed, opening a new avenue for RE energy dissipation using naturally excited waves. Dimensionless parameter scaling of intrinsicmore »« less
Cited by 14
https://doi.org/10.1088/1741-4326/ab024a

Similar Records