Physics basis for an advanced physics and advanced technology tokamak power plant configuration: ARIES-ACT1

Kessel, C. E.; Poli, F. M.; Ghantous, K.; Gorelenkov, N. N.; Rensink, M. E.; Rognlien, T. D.; Snyder, P. B.; St. John, H.; Turnbull, A. D.

doi:10.13182/FST14-795

Title: Physics basis for an advanced physics and advanced technology tokamak power plant configuration: ARIES-ACT1

Journal Article · Thu Jan 01 00:00:00 EST 2015 · Fusion Science and Technology

DOI:https://doi.org/10.13182/FST14-795· OSTI ID:1297641

Kessel, C. E. ^[1]; Poli, F. M. ^[1]; Ghantous, K. ^[1]; Gorelenkov, N. N. ^[1]; Rensink, M. E. ^[2]; Rognlien, T. D. ^[2]; Snyder, P. B. ^[3]; St. John, H. ^[3]; Turnbull, A. D. ^[3]

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

Here, the advanced physics and advanced technology tokamak power plant ARIES-ACT1 has a major radius of 6.25 m at an aspect ratio of 4.0, toroidal field of 6.0 T, strong shaping with elongation of 2.2, and triangularity of 0.63. The broadest pressure cases reached wall-stabilized β_N ~ 5.75, limited by n = 3 external kink mode requiring a conducting shell at b/a = 0.3, requiring plasma rotation, feedback, and/or kinetic stabilization. The medium pressure peaking case reaches β_N = 5.28 with B_T = 6.75, while the peaked pressure case reaches β_N < 5.15. Fast particle magnetohydrodynamic stability shows that the alpha particles are unstable, but this leads to redistribution to larger minor radius rather than loss from the plasma. Edge and divertor plasma modeling shows that 75% of the power to the divertor can be radiated with an ITER-like divertor geometry, while >95% can be radiated in a stable detached mode with an orthogonal target and wide slot geometry. The bootstrap current fraction is 91% with a q95 of 4.5, requiring ~1.1 MA of external current drive. This current is supplied with 5 MW of ion cyclotron radio frequency/fast wave and 40 MW of lower hybrid current drive. Electron cyclotron is most effective for safety factor control over ρ~0.2 to 0.6 with 20 MW. The pedestal density is ~0.9×10²⁰/m³, and the temperature is ~4.4 keV. The H98 factor is 1.65, n/n_Gr = 1.0, and the ratio of net power to threshold power is 2.8 to 3.0 in the flattop.

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Research Organization:: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC52-07NA27344

OSTI ID:: 1297641

Report Number(s):: LLNL-JRNL-640706

Journal Information:: Fusion Science and Technology, Journal Name: Fusion Science and Technology; ISSN 1536-1055

Publisher:: American Nuclear SocietyCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 11 works

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The EPED pedestal model and edge localized mode-suppressed regimes: Studies of quiescent H-mode and development of a model for edge localized mode suppression via resonant magnetic perturbations Snyder, P. B.; Osborne, T. H.; Burrell, K. H. Physics of Plasmas, Vol. 19, Issue 5 https://doi.org/10.1063/1.3699623	journal	May 2012
Advances towards QH-mode viability for ELM-stable operation in ITER Garofalo, A. M.; Solomon, W. M.; Park, J. -K. Nuclear Fusion, Vol. 51, Issue 8 https://doi.org/10.1088/0029-5515/51/8/083018	journal	July 2011
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