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Title: Core plasma physics basis and its impacts on the FNSF

Journal Article · · Fusion Engineering and Design
 [1];  [2];  [3];  [4];  [4];  [5];  [3];  [3]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  4. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  5. General Atomics, La Jolla, CA (United States)

The FNSF core plasma physics is reportede on with detailed analysis to establish the basis for the reference configuration, R = 4.8 m, a = 1.2 m, Ip = 7.87 MA, and BT = 7.5 T, q95 = 6, fBS = 0.52, βN < 2.7 established in Ref. [1]. Central solenoid (CS) and poloidal field (PF) coils are far from the plasma as in a power plant, and acceptable coil currents are determined for the rampup and flattop fiducial states. Time-dependent free-boundary plasma evolution simulations demonstrate that the FNSF plasma can be established, ramped up, and relaxed into flattop, including vertical stabilizers, internal feedback coils and feedback control on plasma current, position, and shape. A range of density (no/ = 1.3–1.5) and temperature (To/ = 2.2–2.7) profiles are examined, indicating that energy confinement of H98 = 1.1–1.2 is required to provide 100% non-inductive plasma current in the FNSF. GLF23 theory based transport model predicted lower energy confinement of H98 ~0.6–0.85. The EPED analysis shows that the pedestal temperature ranges from 4.0–4.7 keV for pedestal densities of 1.7–1.0 × 1020/m3. The n = 1 kink stability shows no-wall beta limits, using the pressure and current profiles associated with the transport and current drive sources, ranging from βN ~2.25–2.55 depending on li. A conducting wall can extend these limits by 10–40% depending on li and wall location. At the lower beta’s of the reference plasma, a combination of 50 MW of NB, 30 MW of LH, 20 MW of ICRF, 20 MW of EC, and bootstrap current, are found to provide 100% of the plasma current with a stable current profile. Impacts on the FNSF of plasma physics are discussed and R&D challenges are recorded.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
AC52-07NA27344; AC02-09CH11466; FC02-99ER54512; AC05-00OR22725
OSTI ID:
1542740
Report Number(s):
LLNL-JRNL-770166; 961634
Journal Information:
Fusion Engineering and Design, Vol. 135, Issue PB; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 14 works
Citation information provided by
Web of Science

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Cited By (3)

Potential Impacts of Liquid-Metal Plasma-Facing Components on Heating and Current Drive Actuators for a Fusion Nuclear Science Facility journal July 2019
High field side lower hybrid wave launch for steady state plasma sustainment journal November 2018
Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility journal June 2019

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