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Assessment of the baseline scenario at q95~ 3 for ITER

Journal Article · · Nuclear Fusion
 [1];  [2];  [3];  [4];  [5];  [2];  [5];  [6];  [7];  [8];  [9];  [10];  [2];  [9];  [11];  [2];  [12];  [8]
  1. Culham Science Centre (United Kingdom of Great Britain and Northern Ireland); European Commission, Brussels (Belgium); General Atomics
  2. Max-Planck-Institut für Plasmaphysik, Garching (Germany)
  3. General Atomics, San Diego, CA (United States); ITER Organization, St. Paul lez Durance (France)
  4. Massachusetts Institute of Technology (MIT), Cambridge, MA (United States)
  5. National Institutes for Quantum Radiology Science and Technology, Ibaraki (Japan)
  6. CEA, IRFM, Saint-Paul-lez-Durance (France); Culham Science Centre (United Kingdom of Great Britain and Northern Ireland)
  7. Princeton University, NJ (United States)
  8. ITER Organization, St. Paul lez Durance (France)
  9. Culham Science Centre (United Kingdom of Great Britain and Northern Ireland)
  10. Universidade de Lisboa (Portugal); Culham Science Centre (United Kingdom of Great Britain and Northern Ireland); Princeton University, NJ (United States)
  11. General Atomics, San Diego, CA (United States)
  12. General Atomics, San Diego, CA (United States); Columbia University, New York, NY (United States)

The International Tokamak Physics Activity topical group on integrated operational scenarios has compiled a database of stationary H-mode discharges at q95 ~ 3 from AUG, C-Mod, DIII-D, JET and JT-60U, for both carbon wall and high-Z metal wall experiments with ~3300 entries. The analyses focus on discharges that are stationary for ≥5 thermal energy confinement times to evaluate the baseline scenario proposed for ITER at 15 MA for achieving its goals of Q = 10, fusion power of 500 MW at normalized pressure, βN = 1.8 and normalized confinement as predicted by the standard H-mode scaling, H98y2 = 1. With the data restricted to stationary H-modes at q95 ~ 3, the database shows significant variation of thermal energy confinement compared to the standard H-mode scaling (IPB98(y,2)) in dimensionless form. The data show similar scaling with normalized gyro-radius, but more favorable scaling towards lower collision frequency and more favorable scaling with plasma beta. Using all the engineering variables employed in IPB98(y,2), results in an overfit due to correlations among the data. Furthermore, there are significant residual trends in the confinement for plasma current, device size, loss power, and in particular for the plasma density. Significant differences between results obtained for devices with a carbon wall and high-Z metal wall are observed in the data, with data from carbon wall devices providing a larger operating space, encompassing ITER parameters or even exceeding them. H-modes in high-Z metal wall devices have, so-far, not accessed conditions at low collision frequencies, have lower normalized confinement (H98y2 ~ 0.8–0.9) at low input power or beta, achieving H98y2 ~ 1.0 only at input powers two times the L- to H-mode transition scaling predictions and at βN ~ 2.0. Hence, only the best H-modes with high-Z metal walls reach ITER baseline performance requirements.

Research Organization:
General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
FC02-04ER54698; FC02-99ER54512
OSTI ID:
1983556
Alternate ID(s):
OSTI ID: 22929556
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 12 Vol. 58; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

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