Physics basis for the advanced tokamak fusion power plant, ARIES-AT

S. C. Jardin; C. E. Kessel; T. K. Mau; R. L. Miller; F. Najmabadi; V. S. Chan; M. S. Chu; R. Lahaye; L. L. Lao; T. W. Petrie; P. Politzer; H. E. St. John; P. Snyder; G. M. Staebler; A. D. Turnbull; W. P. West

doi:10.1016/j.fusengdes.2005.06.352

Physics basis for the advanced tokamak fusion power plant, ARIES-AT

S. C. Jardin, C. E. Kessel, T. K. Mau, R. L. Miller, F. Najmabadi, V. S. Chan, M. S. Chu, R. Lahaye, L. L. Lao, T. W. Petrie, P. Politzer, H. E. St. John, P. Snyder, G. M. Staebler, A. D. Turnbull, W. P. West

Research output: Contribution to journal › Article › peer-review

44 Scopus citations

Abstract

The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A≡R/a=4.0, an elongation and triangularity of κ=2.20,δ=0.90 (evaluated at the separatrix surface), a toroidal beta of β=9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of βN≡100×β/(IP(MA)/a(m)B(T))=5.4. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is fBS≡IBS/IP=0.91. This leads to a design with total plasma current IP=12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.

Original language	English
Pages (from-to)	25-62
Number of pages	38
Journal	Fusion Engineering and Design
Volume	80
Issue number	1-4
DOIs	https://doi.org/10.1016/j.fusengdes.2005.06.352
State	Published - Jan 2006
Externally published	Yes

Keywords

Advanced tokamak
Fusion power plant
Physics basis
Reactor studies

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.fusengdes.2005.06.352

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Jardin, S. C., Kessel, C. E., Mau, T. K., Miller, R. L., Najmabadi, F., Chan, V. S., Chu, M. S., Lahaye, R., Lao, L. L., Petrie, T. W., Politzer, P., St. John, H. E., Snyder, P., Staebler, G. M., Turnbull, A. D., & West, W. P. (2006). Physics basis for the advanced tokamak fusion power plant, ARIES-AT. Fusion Engineering and Design, 80(1-4), 25-62. https://doi.org/10.1016/j.fusengdes.2005.06.352

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title = "Physics basis for the advanced tokamak fusion power plant, ARIES-AT",

abstract = "The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A≡R/a=4.0, an elongation and triangularity of κ=2.20,δ=0.90 (evaluated at the separatrix surface), a toroidal beta of β=9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of βN≡100×β/(IP(MA)/a(m)B(T))=5.4. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is fBS≡IBS/IP=0.91. This leads to a design with total plasma current IP=12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.",

keywords = "Advanced tokamak, Fusion power plant, Physics basis, Reactor studies",

author = "Jardin, {S. C.} and Kessel, {C. E.} and Mau, {T. K.} and Miller, {R. L.} and F. Najmabadi and Chan, {V. S.} and Chu, {M. S.} and R. Lahaye and Lao, {L. L.} and Petrie, {T. W.} and P. Politzer and {St. John}, {H. E.} and P. Snyder and Staebler, {G. M.} and Turnbull, {A. D.} and West, {W. P.}",

year = "2006",

month = jan,

doi = "10.1016/j.fusengdes.2005.06.352",

language = "English",

volume = "80",

pages = "25--62",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

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Jardin, SC, Kessel, CE, Mau, TK, Miller, RL, Najmabadi, F, Chan, VS, Chu, MS, Lahaye, R, Lao, LL, Petrie, TW, Politzer, P, St. John, HE, Snyder, P, Staebler, GM, Turnbull, AD & West, WP 2006, 'Physics basis for the advanced tokamak fusion power plant, ARIES-AT', Fusion Engineering and Design, vol. 80, no. 1-4, pp. 25-62. https://doi.org/10.1016/j.fusengdes.2005.06.352

TY - JOUR

T1 - Physics basis for the advanced tokamak fusion power plant, ARIES-AT

AU - Jardin, S. C.

AU - Kessel, C. E.

AU - Mau, T. K.

AU - Miller, R. L.

AU - Najmabadi, F.

AU - Chan, V. S.

AU - Chu, M. S.

AU - Lahaye, R.

AU - Lao, L. L.

AU - Petrie, T. W.

AU - Politzer, P.

AU - St. John, H. E.

AU - Snyder, P.

AU - Staebler, G. M.

AU - Turnbull, A. D.

AU - West, W. P.

PY - 2006/1

Y1 - 2006/1

N2 - The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A≡R/a=4.0, an elongation and triangularity of κ=2.20,δ=0.90 (evaluated at the separatrix surface), a toroidal beta of β=9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of βN≡100×β/(IP(MA)/a(m)B(T))=5.4. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is fBS≡IBS/IP=0.91. This leads to a design with total plasma current IP=12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.

AB - The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A≡R/a=4.0, an elongation and triangularity of κ=2.20,δ=0.90 (evaluated at the separatrix surface), a toroidal beta of β=9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of βN≡100×β/(IP(MA)/a(m)B(T))=5.4. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is fBS≡IBS/IP=0.91. This leads to a design with total plasma current IP=12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.

KW - Advanced tokamak

KW - Fusion power plant

KW - Physics basis

KW - Reactor studies

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DO - 10.1016/j.fusengdes.2005.06.352

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SN - 0920-3796

VL - 80

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EP - 62

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 1-4

ER -

Physics basis for the advanced tokamak fusion power plant, ARIES-AT

Abstract

Keywords

UN SDGs

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