Simplifying the ST and AT Concepts

R. Raman; T. R. Jarboe; J. E. Menard; M. Ono; G. Taylor; B. A. Nelson; D. Mueller; T. Brown

doi:10.1007/s10894-015-0040-3

Simplifying the ST and AT Concepts

R. Raman
, T. R. Jarboe
, J. E. Menard
, M. Ono
, G. Taylor
, B. A. Nelson
, D. Mueller
, T. Brown

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

4 Scopus citations

Abstract

As stated in a IEA Burning Plasma Workshop Review (Donné et al. in Fusion Sci Technol 49:79, 2006) “…there is not much flexibility in the fueling of ITER”. High-performance tokamak and ST plasmas greatly benefit from plasma rotation and rotation shear to increase energy confinement time and sustain high beta, made possible due to toroidal momentum injection from neutral beams. Advanced ST and AT scenarios rely on optimized density and pressure profiles that must be maintained for efficient device performance. In addition these discharges require the capability for off-axis current drive. Controlled variable-depth deep fueling that also injects toroidal momentum, in combination with the capability for off-axis current drive, would allow the AT/ST concepts to operate at close to projected performance levels. Advanced fuelling based on compact toroid injection and Electron Bernstein Wave off-axis current drive in conjunction with solenoid-free plasma start-up are proposed as methods to improve FNSF device performance and simplify the ST/AT Demo.

Original language	English (US)
Pages (from-to)	34-40
Number of pages	7
Journal	Journal of Fusion Energy
Volume	35
Issue number	1
DOIs	https://doi.org/10.1007/s10894-015-0040-3
State	Published - Feb 1 2016

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Keywords

AT
CHI
Compact toroid
CT
Current drive
EBW
Fueling
Momentum
Simplifying fusion
Spherical torus
ST
Steady state
Tokamak

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10.1007/s10894-015-0040-3

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title = "Simplifying the ST and AT Concepts",

abstract = "As stated in a IEA Burning Plasma Workshop Review (Donn{\'e} et al. in Fusion Sci Technol 49:79, 2006) “…there is not much flexibility in the fueling of ITER”. High-performance tokamak and ST plasmas greatly benefit from plasma rotation and rotation shear to increase energy confinement time and sustain high beta, made possible due to toroidal momentum injection from neutral beams. Advanced ST and AT scenarios rely on optimized density and pressure profiles that must be maintained for efficient device performance. In addition these discharges require the capability for off-axis current drive. Controlled variable-depth deep fueling that also injects toroidal momentum, in combination with the capability for off-axis current drive, would allow the AT/ST concepts to operate at close to projected performance levels. Advanced fuelling based on compact toroid injection and Electron Bernstein Wave off-axis current drive in conjunction with solenoid-free plasma start-up are proposed as methods to improve FNSF device performance and simplify the ST/AT Demo.",

keywords = "AT, CHI, Compact toroid, CT, Current drive, EBW, Fueling, Momentum, Simplifying fusion, Spherical torus, ST, Steady state, Tokamak",

author = "R. Raman and Jarboe, \{T. R.\} and Menard, \{J. E.\} and M. Ono and G. Taylor and Nelson, \{B. A.\} and D. Mueller and T. Brown",

note = "Publisher Copyright: {\textcopyright} 2015, Springer Science+Business Media New York.",

year = "2016",

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doi = "10.1007/s10894-015-0040-3",

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AU - Raman, R.

AU - Jarboe, T. R.

AU - Menard, J. E.

AU - Ono, M.

AU - Taylor, G.

AU - Nelson, B. A.

AU - Mueller, D.

AU - Brown, T.

PY - 2016/2/1

Y1 - 2016/2/1

N2 - As stated in a IEA Burning Plasma Workshop Review (Donné et al. in Fusion Sci Technol 49:79, 2006) “…there is not much flexibility in the fueling of ITER”. High-performance tokamak and ST plasmas greatly benefit from plasma rotation and rotation shear to increase energy confinement time and sustain high beta, made possible due to toroidal momentum injection from neutral beams. Advanced ST and AT scenarios rely on optimized density and pressure profiles that must be maintained for efficient device performance. In addition these discharges require the capability for off-axis current drive. Controlled variable-depth deep fueling that also injects toroidal momentum, in combination with the capability for off-axis current drive, would allow the AT/ST concepts to operate at close to projected performance levels. Advanced fuelling based on compact toroid injection and Electron Bernstein Wave off-axis current drive in conjunction with solenoid-free plasma start-up are proposed as methods to improve FNSF device performance and simplify the ST/AT Demo.

AB - As stated in a IEA Burning Plasma Workshop Review (Donné et al. in Fusion Sci Technol 49:79, 2006) “…there is not much flexibility in the fueling of ITER”. High-performance tokamak and ST plasmas greatly benefit from plasma rotation and rotation shear to increase energy confinement time and sustain high beta, made possible due to toroidal momentum injection from neutral beams. Advanced ST and AT scenarios rely on optimized density and pressure profiles that must be maintained for efficient device performance. In addition these discharges require the capability for off-axis current drive. Controlled variable-depth deep fueling that also injects toroidal momentum, in combination with the capability for off-axis current drive, would allow the AT/ST concepts to operate at close to projected performance levels. Advanced fuelling based on compact toroid injection and Electron Bernstein Wave off-axis current drive in conjunction with solenoid-free plasma start-up are proposed as methods to improve FNSF device performance and simplify the ST/AT Demo.

KW - AT

KW - CHI

KW - Compact toroid

KW - CT

KW - Current drive

KW - EBW

KW - Fueling

KW - Momentum

KW - Simplifying fusion

KW - Spherical torus

KW - ST

KW - Steady state

KW - Tokamak

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JO - Journal of Fusion Energy

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Simplifying the ST and AT Concepts

Abstract

All Science Journal Classification (ASJC) codes

Keywords

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