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Title: Development of an integrated core–edge scenario using the super H-mode

Journal Article · · Nuclear Fusion
ORCiD logo [1]; ORCiD logo [2]; ORCiD logo [3]; ORCiD logo [2]; ORCiD logo [4]; ORCiD logo [2]; ORCiD logo [5]; ORCiD logo [4]; ORCiD logo [4];  [2]; ORCiD logo [6]; ORCiD logo [2]; ORCiD logo [7]; ORCiD logo [2]; ORCiD logo [5]; ORCiD logo [1]
  1. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Sciences and Fusion Center
  2. General Atomics, San Diego, CA (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  5. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  6. Columbia Univ., New York, NY (United States)
  7. Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA (United States)

An optimized pedestal regime called the super-H (SH) mode is leveraged to couple a fusion relevant core plasma with a high density scrape-off layer appropriate for realistic reactor power exhaust solutions. Recent DIII-D experiments have expanded the operating space of the SH regime using advanced control algorithms and investigated optimization of impurity seeding, deuterium gas puffing, and 3D magnetic perturbations. Simultaneous real-time control of the pedestal density and radiated power with in-vessel coils and nitrogen seeding enable optimal coupled divertor and pedestal conditions. Four case studies are analysed with varied levels of radiated power in the divertor volume ranging from 0 (no seeding) to 8.5 MW radiated from carbon and nitrogen emission. Plasmas with a 4.5 MW radiated power target establish a radiative mantle, leading to divertor temperatures of ~16 eV while maintaining SH-mode, and with only marginal impact on the pedestal and core performance. Increased levels of N2 seeding with a 7.5 MW radiated power target facilitate detachment onset and divertor temperatures <5 eV, with no degradation in stored energy and the operational point remaining inside the SH-mode channel for >2.5 τE. Finally, a 8.5 MW radiated power target leads to partial detachment, which is so far associated with the loss of access to SH-mode pedestal conditions.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); General Atomics, San Diego, CA (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC05-00OR22725; FC02-04ER54698; SC0014264; FG02-95ER54309; AC52-07NA27344; AC02-09CH11466; AC02-05CH11231; NA0003525
OSTI ID:
1844846
Alternate ID(s):
OSTI ID: 1873630
Report Number(s):
LLNL-JRNL-836400; TRN: US2302400
Journal Information:
Nuclear Fusion, Vol. 61, Issue 12; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (37)

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On the stability and stationarity of the Super H-mode combined with an ion transport barrier in the core journal January 2021
Optimizing the Super H-mode pedestal to improve performance and facilitate divertor integration journal October 2020
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The advanced tokamak path to a compact net electric fusion pilot plant journal March 2021
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