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Advances in the high bootstrap fraction regime on DIII-D towards the Q = 5 mission of ITER steady state

Journal Article · · Nuclear Fusion
 [1];  [2];  [3];  [3];  [3];  [2];  [3];  [4];  [3];  [5];  [6];  [7];  [3];  [3];  [2];  [3]
  1. Chinese Academy of Science, Hefei (People's Republic of China); General Atomics
  2. General Atomics, San Diego, CA (United States)
  3. Chinese Academy of Science, Hefei (People's Republic of China)
  4. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  5. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  6. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  7. Univ. of Wisconsin, Madison, WI (United States)
Recent EAST/DIII-D joint experiments on the high poloidal beta $${{\beta}_{\text{P}}}$$ regime in DIII-D have extended operation with internal transport barriers (ITBs) and excellent energy confinement (H 98y2 ~ 1.6) to higher plasma current, for lower q 95 ≤ 7.0, and more balanced neutral beam injection (NBI) (torque injection < 2 Nm), for lower plasma rotation than previous results. Transport analysis and experimental measurements at low toroidal rotation suggest that the E × B shear effect is not key to the ITB formation in these high $${{\beta}_{\text{P}}}$$ discharges. Experiments and TGLF modeling show that the Shafranov shift has a key stabilizing effect on turbulence. Extrapolation of the DIII-D results using a 0D model shows that with the improved confinement, the high bootstrap fraction regime could achieve fusion gain Q = 5 in ITER at $${{\beta}_{\text{N}}}$$ ~ 2.9 and q 95 ~ 7. With the optimization of q(0), the required improved confinement is achievable when using 1.5D TGLF-SAT1 for transport simulations. Furthermore, results reported in this paper suggest that the DIII-D high $${{\beta}_{\text{P}}}$$ scenario could be a candidate for ITER steady state operation.
Research Organization:
General Atomics, San Diego, CA (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
National Magnetic Confinement Fusion Program of China; USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC02-09CH11466; AC52-07NA27344; FC02-04ER54698; FG02-06ER54871; FG02-07ER54917; FG02-08ER54999
OSTI ID:
1374829
Alternate ID(s):
OSTI ID: 1838265
OSTI ID: 22738408
OSTI ID: 22925694
Report Number(s):
LLNL-JRNL--830401
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 5 Vol. 57; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (10)

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Tokamak profile prediction using direct gyrokinetic and neoclassical simulation journal June 2009
Progress toward steady-state tokamak operation exploiting the high bootstrap current fraction regime journal June 2016
Gyrofluid simulations of turbulence suppression in reversed-shear experiments on the Tokamak Fusion Test Reactor journal May 1997
Separation of β̄ p and ℓ i in tokamaks of non-circular cross-section journal October 1985
Chapter 6: Steady state operation journal June 2007
Advances towards QH-mode viability for ELM-stable operation in ITER journal July 2011
A new paradigm for E × B velocity shear suppression of gyro-kinetic turbulence and the momentum pinch journal September 2013
Compatibility of internal transport barrier with steady-state operation in the high bootstrap fraction regime on DIII-D journal November 2015
Fusion Nuclear Science Facility Candidates journal February 2011

Cited By (3)

Transport barriers in bootstrap-driven tokamaks journal May 2018
Integrated modeling of plasma ramp-up in DIII-D ITER-like and high bootstrap current scenario discharges journal April 2018
Study of Alfven eigenmodes stability in plasma with multiple NBI driven energetic particle species journal June 2019

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