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Title: Advances in the steady-state hybrid regime in DIII-D – a fully non-inductive, ELM-suppressed scenario for ITER

Abstract

Here, the hybrid regime with beta, collisionality, safety factor and plasma shape relevant to the ITER steady-state mission has been successfully integrated with ELM suppression by applying an odd parity n=3 resonant magnetic perturbation (RMP). Fully non-inductive hybrids in the DIII-D tokamak with high beta (β ≤ 2.8%) and high confinement (98y2 ≤ 1.4) in the ITER similar shape have achieved zero surface loop voltage for up to two current relaxation times using efficient central current drive from ECCD and NBCD. The n=3 RMP causes surprisingly little increase in thermal transport during ELM suppression. Poloidal magnetic flux pumping in hybrid plasmas maintains q above 1 without loss of current drive efficiency, except that experiments show that extremely peaked ECCD profiles can create sawteeth. During ECCD, Alfvén eigenmode (AE) activity is replaced by a more benign fishbone-like mode, reducing anomalous beam ion diffusion by a factor of 2. While the electron and ion thermal diffusivities substantially increase with higher ECCD power, the loss of confinement can be offset by the decreased fast ion transport resulting from AE suppression. Extrapolations from DIII-D along a dimensionless parameter scaling path as well as those using self-consistent theory-based modeling show that these ELM-suppressed, fully non-inductivemore » hybrids can achieve the Q = 5 ITER steady-state mission.« less

Authors:
 [1];  [2];  [3];  [4]; ORCiD logo [1];  [2];  [1];  [2];  [1];  [1];  [2];  [5];  [1];  [2];  [1];  [5];  [2];  [1];  [6];  [7] more »;  [1];  [1];  [1];  [1];  [1];  [1];  [8];  [8];  [1];  [9] « less
  1. General Atomics, San Diego, CA (United States)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. Columbia Univ., New York, NY (United States)
  5. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  6. Univ. of Wisconsin, Madison, WI (United States)
  7. Univ. of California San Diego, La Jolla, CA (United States)
  8. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  9. Univ. of California, Irvine, CA (United States)
Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); General Atomics, San Diego, CA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1373696
Alternate Identifier(s):
OSTI ID: 1374556
Grant/Contract Number:
AC05-06OR23100; AC02-09CH11466; FC02-05ER54809; FG02-04ER54761; FG02-08ER54999; AC52-07NA27344; FC02-04ER54698; SC-G903402
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 57; Journal Issue: 11; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats

Petty, Craig C., Nazikian, Raffi, Park, Jin Myung, Turco, Francesca, Chen, Xi, Cui, Lang, Evans, Todd E., Ferraro, N. M., Ferron, John R., Garofalo, Andrea M., Grierson, B. A., Holcomb, Chris T., Hyatt, A. W., Kolemen, Egemen, La Haye, Robert John, Lasnier, Charles, Logan, Nikolas, Luce, Timothy C., McKee, George R., Orlov, Dmitri M., Osborne, Tom H., Pace, David C., Paz-Soldan, Carlos, Petrie, Tom W., Snyder, Philip B., Solomon, Wayne M., Taylor, Nicholas Z., Thome, Kathreen E., Van Zeeland, Michael A., and Zhu, Yubao. Advances in the steady-state hybrid regime in DIII-D – a fully non-inductive, ELM-suppressed scenario for ITER. United States: N. p., 2017. Web. doi:10.1088/1741-4326/aa80ab.
Petty, Craig C., Nazikian, Raffi, Park, Jin Myung, Turco, Francesca, Chen, Xi, Cui, Lang, Evans, Todd E., Ferraro, N. M., Ferron, John R., Garofalo, Andrea M., Grierson, B. A., Holcomb, Chris T., Hyatt, A. W., Kolemen, Egemen, La Haye, Robert John, Lasnier, Charles, Logan, Nikolas, Luce, Timothy C., McKee, George R., Orlov, Dmitri M., Osborne, Tom H., Pace, David C., Paz-Soldan, Carlos, Petrie, Tom W., Snyder, Philip B., Solomon, Wayne M., Taylor, Nicholas Z., Thome, Kathreen E., Van Zeeland, Michael A., & Zhu, Yubao. Advances in the steady-state hybrid regime in DIII-D – a fully non-inductive, ELM-suppressed scenario for ITER. United States. doi:10.1088/1741-4326/aa80ab.
Petty, Craig C., Nazikian, Raffi, Park, Jin Myung, Turco, Francesca, Chen, Xi, Cui, Lang, Evans, Todd E., Ferraro, N. M., Ferron, John R., Garofalo, Andrea M., Grierson, B. A., Holcomb, Chris T., Hyatt, A. W., Kolemen, Egemen, La Haye, Robert John, Lasnier, Charles, Logan, Nikolas, Luce, Timothy C., McKee, George R., Orlov, Dmitri M., Osborne, Tom H., Pace, David C., Paz-Soldan, Carlos, Petrie, Tom W., Snyder, Philip B., Solomon, Wayne M., Taylor, Nicholas Z., Thome, Kathreen E., Van Zeeland, Michael A., and Zhu, Yubao. Wed . "Advances in the steady-state hybrid regime in DIII-D – a fully non-inductive, ELM-suppressed scenario for ITER". United States. doi:10.1088/1741-4326/aa80ab. https://www.osti.gov/servlets/purl/1373696.
@article{osti_1373696,
title = {Advances in the steady-state hybrid regime in DIII-D – a fully non-inductive, ELM-suppressed scenario for ITER},
author = {Petty, Craig C. and Nazikian, Raffi and Park, Jin Myung and Turco, Francesca and Chen, Xi and Cui, Lang and Evans, Todd E. and Ferraro, N. M. and Ferron, John R. and Garofalo, Andrea M. and Grierson, B. A. and Holcomb, Chris T. and Hyatt, A. W. and Kolemen, Egemen and La Haye, Robert John and Lasnier, Charles and Logan, Nikolas and Luce, Timothy C. and McKee, George R. and Orlov, Dmitri M. and Osborne, Tom H. and Pace, David C. and Paz-Soldan, Carlos and Petrie, Tom W. and Snyder, Philip B. and Solomon, Wayne M. and Taylor, Nicholas Z. and Thome, Kathreen E. and Van Zeeland, Michael A. and Zhu, Yubao},
abstractNote = {Here, the hybrid regime with beta, collisionality, safety factor and plasma shape relevant to the ITER steady-state mission has been successfully integrated with ELM suppression by applying an odd parity n=3 resonant magnetic perturbation (RMP). Fully non-inductive hybrids in the DIII-D tokamak with high beta (β ≤ 2.8%) and high confinement (98y2 ≤ 1.4) in the ITER similar shape have achieved zero surface loop voltage for up to two current relaxation times using efficient central current drive from ECCD and NBCD. The n=3 RMP causes surprisingly little increase in thermal transport during ELM suppression. Poloidal magnetic flux pumping in hybrid plasmas maintains q above 1 without loss of current drive efficiency, except that experiments show that extremely peaked ECCD profiles can create sawteeth. During ECCD, Alfvén eigenmode (AE) activity is replaced by a more benign fishbone-like mode, reducing anomalous beam ion diffusion by a factor of 2. While the electron and ion thermal diffusivities substantially increase with higher ECCD power, the loss of confinement can be offset by the decreased fast ion transport resulting from AE suppression. Extrapolations from DIII-D along a dimensionless parameter scaling path as well as those using self-consistent theory-based modeling show that these ELM-suppressed, fully non-inductive hybrids can achieve the Q = 5 ITER steady-state mission.},
doi = {10.1088/1741-4326/aa80ab},
journal = {Nuclear Fusion},
number = 11,
volume = 57,
place = {United States},
year = {Wed Jul 19 00:00:00 EDT 2017},
month = {Wed Jul 19 00:00:00 EDT 2017}
}

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