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

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

doi:10.1088/1741-4326/aa80ab

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

Journal Article · Wed Jul 19 00:00:00 EDT 2017 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/aa80ab· OSTI ID:1373696

Petty, Craig C. ^[1]; Nazikian, Raffi ^[2]; Park, Jin Myung ^[3]; Turco, Francesca ^[4]; ^[1]; Cui, Lang ^[2]; Evans, Todd E. ^[1]; Ferraro, N. M. ^[2]; Ferron, John R. ^[1]; Garofalo, Andrea M. ^[1]; Grierson, B. A. ^[2]; Holcomb, Chris T. ^[5]; Hyatt, A. W. ^[1]; Kolemen, Egemen ^[2]; La Haye, Robert John ^[1]; Lasnier, Charles ^[5]; Logan, Nikolas ^[2]; Luce, Timothy C. ^[1]; McKee, George R. ^[6]; Orlov, Dmitri M. ^[7] more »

General Atomics, San Diego, CA (United States)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Columbia Univ., New York, NY (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Univ. of Wisconsin, Madison, WI (United States)
Univ. of California San Diego, La Jolla, CA (United States)
Oak Ridge Associated Univ., Oak Ridge, TN (United States)
Univ. of California, Irvine, CA (United States)

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 (H_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_fus = 5 ITER steady-state mission.

View Accepted Manuscript (DOE)

Research Organization:: General Atomics, San Diego, CA (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: USDOE; USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC02-09CH11466; AC05-06OR23100; AC52-07NA27344; FC02-04ER54698; FG02-04ER54761; FG02-08ER54999

OSTI ID:: 1373696

Alternate ID(s):: OSTI ID: 1845199
OSTI ID: 1374556
OSTI ID: 22738407
OSTI ID: 22925877

Report Number(s):: LLNL-JRNL-830740

Journal Information:: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 11 Vol. 57; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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

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