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

Abstract

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 cyclotronmore »« less

Authors:

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)

Publication Date:: Thu Jan 01 00:00:00 EST 2015

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

Sponsoring Org.:: USDOE

OSTI Identifier:: 1297641

Report Number(s):: LLNL-JRNL-640706
Journal ID: ISSN 1536-1055

Grant/Contract Number:: AC52-07NA27344

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Science and Technology

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

Publisher:: American Nuclear Society

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION

Citation Formats


                    Kessel, C. E., Poli, F. M., Ghantous, K., Gorelenkov, N. N., Rensink, M. E., Rognlien, T. D., Snyder, P. B., St. John, H., and Turnbull, A. D. Physics basis for an advanced physics and advanced technology tokamak power plant configuration: ARIES-ACT1.  United States: N. p., 2015. 
Web.  doi:10.13182/FST14-795.

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                    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. Physics basis for an advanced physics and advanced technology tokamak power plant configuration: ARIES-ACT1.  United States.  https://doi.org/10.13182/FST14-795

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                    Kessel, C. E., Poli, F. M., Ghantous, K., Gorelenkov, N. N., Rensink, M. E., Rognlien, T. D., Snyder, P. B., St. John, H., and Turnbull, A. D. Thu .  
"Physics basis for an advanced physics and advanced technology tokamak power plant configuration: ARIES-ACT1".  United States.  https://doi.org/10.13182/FST14-795.  https://www.osti.gov/servlets/purl/1297641.

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@article{osti_1297641,

  title        = {Physics basis for an advanced physics and advanced technology tokamak power plant configuration: ARIES-ACT1},

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

  abstractNote = {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 βN ~ 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 βN = 5.28 with BT = 6.75, while the peaked pressure case reaches βN < 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/nGr = 1.0, and the ratio of net power to threshold power is 2.8 to 3.0 in the flattop.},

  doi          = {10.13182/FST14-795},

  journal      = {Fusion Science and Technology},

  number       = ,

  volume       = ,

  place        = {United States},

  year         = {Thu Jan 01 00:00:00 EST 2015},

  month        = {Thu Jan 01 00:00:00 EST 2015}

}

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Plasma Physics and Controlled Fusion, Vol. 51, Issue 3
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Snyder, P. B.; Burrell, K. H.; Wilson, H. R.
Nuclear Fusion, Vol. 47, Issue 8
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Evans, Todd E.; Moyer, Richard A.; Burrell, Keith H.
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In-vessel saddle coils for MHD control in ASDEX Upgrade
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Suttrop, W.; Gruber, O.; Günter, S.
Fusion Engineering and Design, Vol. 84, Issue 2-6
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Active Control of Type-I Edge-Localized Modes with $n = 1$ Perturbation Fields in the JET Tokamak
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Liang, Y.; Koslowski, H. R.; Thomas, P. R.
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Resonant magnetic perturbation experiments on MAST using external and internal coils for ELM control
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Kirk, A.; Nardon, E.; Akers, R.
Nuclear Fusion, Vol. 50, Issue 3
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Investigation of resistive wall mode stabilization physics in high-beta plasmas using applied non-axisymmetric fields in NSTX
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Sontag, A. C.; Sabbagh, S. A.; Zhu, W.
Nuclear Fusion, Vol. 47, Issue 8
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Suppression of Edge Localized Modes in High-Confinement KSTAR Plasmas by Nonaxisymmetric Magnetic Perturbations
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Jeon, Y. M.; Park, J. -K.; Yoon, S. W.
Physical Review Letters, Vol. 109, Issue 3
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Magnetic Topology Changes Induced by Lower Hybrid Waves and their Profound Effect on Edge-Localized Modes in the EAST Tokamak
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Liang, Y.; Gong, X. Z.; Gan, K. F.
Physical Review Letters, Vol. 110, Issue 23
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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
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Snyder, P. B.; Osborne, T. H.; Burrell, K. H.
Physics of Plasmas, Vol. 19, Issue 5
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Advances towards QH-mode viability for ELM-stable operation in ITER
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Garofalo, A. M.; Solomon, W. M.; Park, J. -K.
Nuclear Fusion, Vol. 51, Issue 8
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On Demand Triggering of Edge Localized Instabilities Using External Nonaxisymmetric Magnetic Perturbations in Toroidal Plasmas
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Canik, J. M.; Maingi, R.; Evans, T. E.
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Comparison of H-mode barrier width with a model of neutral penetration length
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Groebner, R. J.; Mahdavi, M. A.; Leonard, A. W.
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Burn condition, helium particle confinement and exhaust efficiency
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Sakasai, A.; Takenaga, H.; Kubo, H.
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Zastrow, K. -D; Cox, S. J.; Hellermann, M. G. von
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Pacher, H. D.; Kukushkin, A. S.; Pacher, G. W.
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Pacher, G. W.; Pacher, H. D.; Janeschitz, G.
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Works referencing / citing this record:

Integrated Tokamak modeling: When physics informs engineering and research planning
journal, May 2018

Poli, Francesca Maria
Physics of Plasmas, Vol. 25, Issue 5
DOI: 10.1063/1.5021489

Current drive for stability of thermonuclear plasma reactor
journal, November 2015

Amicucci, L.; Cardinali, A.; Castaldo, C.
Plasma Physics and Controlled Fusion, Vol. 58, Issue 1
DOI: 10.1088/0741-3335/58/1/014042

Survey of heating and current drive for K-DEMO
journal, January 2018

Mikkelsen, D. R.; Kessel, C. E.; Poli, F. M.
Nuclear Fusion, Vol. 58, Issue 3
DOI: 10.1088/1741-4326/aaa4d2

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

Abstract

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Simulation of the hybrid and steady state advanced operating modes in ITER journal, August 2007

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Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime journal, July 1999

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Ideal MHD stability calculations in axisymmetric toroidal coordinate systems journal, January 1983

The second region of stability against ballooning modes journal, April 1981

An iterative metric method for solving the inverse tokamak equilibrium problem journal, September 1980

Stabilization of external modes in tokamaks by resistive walls and plasma rotation journal, April 1994

Stabilization of ideal modes by resistive walls in tokamaks with plasma rotation and its effect on the beta limit journal, May 1995

Stability and control of resistive wall modes in high beta, low rotation DIII-D plasmas journal, August 2007

Feedback stabilization of nonaxisymmetric resistive wall modes in tokamaks. I. Electromagnetic model journal, September 2000

Kinetic analysis of the resistive wall modes in the ITER advanced tokamak scenario journal, June 2009

1.5D quasilinear model and its application on beams interacting with Alfvén eigenmodes in DIII-D journal, September 2012

Beam anisotropy effect on Alfvén eigenmode stability in ITER-like plasmas journal, March 2005

Central flattening of the fast-ion profile in reversed-shear DIII-D discharges journal, June 2008

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A new look at density limits in tokamaks journal, December 1988

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High performance H mode plasmas at densities above the Greenwald limit journal, January 2002

Investigation of the possibility of exceeding the Greenwald density limit during ECRH in T-10 journal, December 2000

Quasistationary High Confinement Discharges with trans-Greenwald Density on TEXTOR-94 journal, September 2000

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Evolution of tungsten degradation under combined high cycle edge-localized mode and steady-state heat loads journal, December 2011

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Plasma profile and shape optimization for the advanced tokamak power plant, ARIES-AT
journal, January 2006

Physics basis for the advanced tokamak fusion power plant, ARIES-AT
journal, January 2006

Physics basis for a reversed shear tokamak power plant
journal, December 1997

An advanced computational algorithm for systems analysis of tokamak power plants
journal, April 2010

Dynamic modeling of transport and positional control of tokamaks
journal, October 1986

Design and Analysis of the ARIES-ACT1 Fusion Power Core
journal, January 2015

Microinstability-based model for anomalous thermal confinement in tokamaks
journal, December 1986

Simulation of the hybrid and steady state advanced operating modes in ITER
journal, August 2007

The role of rotation in tokamak internal transport barriers
journal, March 1997

Predicting core and edge transport barriers in tokamaks using the GLF23 drift-wave transport model
journal, May 2005

Characterization of peeling–ballooning stability limits on the pedestal
journal, April 2004

Plasma Heat-Flux Dispersal for ACT1 Divertor Configurations
journal, January 2015

Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime
journal, July 1999

Power requirement for accessing the H-mode in ITER
journal, July 2008

Ideal MHD stability calculations in axisymmetric toroidal coordinate systems
journal, January 1983

The second region of stability against ballooning modes
journal, April 1981

An iterative metric method for solving the inverse tokamak equilibrium problem
journal, September 1980

Stabilization of external modes in tokamaks by resistive walls and plasma rotation
journal, April 1994

Stabilization of ideal modes by resistive walls in tokamaks with plasma rotation and its effect on the beta limit
journal, May 1995

Stability and control of resistive wall modes in high beta, low rotation DIII-D plasmas
journal, August 2007

Feedback stabilization of nonaxisymmetric resistive wall modes in tokamaks. I. Electromagnetic model
journal, September 2000

Kinetic analysis of the resistive wall modes in the ITER advanced tokamak scenario
journal, June 2009

1.5D quasilinear model and its application on beams interacting with Alfvén eigenmodes in DIII-D
journal, September 2012

Beam anisotropy effect on Alfvén eigenmode stability in ITER-like plasmas
journal, March 2005

Central flattening of the fast-ion profile in reversed-shear DIII-D discharges
journal, June 2008

Measurements and modeling of Alfvén eigenmode induced fast ion transport and loss in DIII-D and ASDEX Upgrade
journal, May 2011

The effect of the fast-ion profile on Alfvén eigenmode stability
journal, August 2013

A new look at density limits in tokamaks
journal, December 1988

Chapter 2: Plasma confinement and transport
journal, December 1999

Recent progress toward high performance above the Greenwald density limit in impurity seeded discharges in limiter and divertor tokamaks
journal, May 2001

High performance H mode plasmas at densities above the Greenwald limit
journal, January 2002

Investigation of the possibility of exceeding the Greenwald density limit during ECRH in T-10
journal, December 2000

Quasistationary High Confinement Discharges with trans-Greenwald Density on TEXTOR-94
journal, September 2000

Improved performance of ELMy H-modes at high density by plasma shaping in JET
journal, August 2002

Dynamic modelling of lower hybrid current drive
journal, June 1994

Steady state long pulse tokamak operation using Lower Hybrid Current Drive
journal, October 2011

An ITER-relevant passive active multijunction launcher for lower hybrid current drive in JET-grade plasmas
journal, July 2011

New techniques for calculating heat and particle source rates due to neutral beam injection in axisymmetric tokamaks
journal, September 1981

ITER ion cyclotron system: Overview and plans
journal, October 2007

Overview of the ITER EC upper launcher
journal, April 2008

Electron cyclotron current drive in low collisionality limit: On parallel momentum conservation
journal, March 2011

Electron cyclotron current drive efficiency in general tokamak geometry
journal, October 2003

Design Performance of Front Steering-Type Electron Cyclotron Launcher for ITER
journal, January 2005

Edge-plasma models and characteristics for magnetic fusion energy devices
journal, July 2002

Scaling laws for edge plasma parameters in ITER from two-dimensional edge modelling
journal, August 2003

Consequences of a reduction of the upstream power SOL width in ITER
journal, July 2013

A review of recent developments in atomic processes for divertors and edge plasmas
journal, April 1995

The Evaluation of the Heat Loading from Steady, Transient and Off-Normal Conditions in ARIES Power Plants
journal, September 2013

ELM-averaged power exhaust on JET
journal, August 2005

Multi-parameter scaling of divertor power load profiles in D, H and He plasmas on JET and implications for ITER
journal, July 2011

Inter-ELM Power Decay Length for JET and ASDEX Upgrade: Measurement and Comparison with Heuristic Drift-Based Model
journal, November 2011

Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks
journal, December 2011

Physics basis and design of the ITER plasma-facing components
journal, August 2011

Recent US activities on advanced He-cooled W-alloy divertor concepts for fusion power plants
journal, January 2011

Experimental Evaluation of the Thermal Hydraulics of Helium-Cooled Divertors
journal, January 2015

Thermomechanical Analysis for an All-Tungsten ARIES Divertor
journal, January 2015

Energy and particle losses during type-I ELMy H-mode in ASDEX Upgrade
journal, August 2003

Characteristics of type I ELM energy and particle losses in existing devices and their extrapolation to ITER
journal, August 2003

Stationary and transient divertor heat flux profiles and extrapolation to ITER
journal, March 2003

Steady-state and transient power handling in JET
journal, September 2003

Characterization of pedestal parameters and edge localized mode energy losses in the Joint European Torus and predictions for the International Thermonuclear Experimental Reactor
journal, May 2004

Power deposition onto plasma facing components in poloidal divertor tokamaks during type-I ELMs and disruptions
journal, March 2005

Transient heat loads in current fusion experiments, extrapolation to ITER and consequences for its operation
journal, March 2007

Type-I ELM power deposition profile width and temporal shape in JET
journal, August 2011

Power load characterization for type-I ELMy H-modes in JET
journal, November 2011

Scaling of H-mode edge pedestal pressure for a Type-I ELM regime in tokamaks
journal, August 2003

Assessment of erosion of the ITER divertor targets during type I ELMs
journal, August 2003

The latest results from ELM-simulation experiments in plasma accelerators
journal, December 2009

Evolution of tungsten degradation under combined high cycle edge-localized mode and steady-state heat loads
journal, December 2011

Timescale and magnitude of plasma thermal energy loss before and during disruptions in JET
journal, October 2005

Energy flow during disruptions in JET
journal, March 2005

Heat load measurements on the JET first wall during disruptions
journal, August 2011

Magnetic energy flows during the current quench and termination of disruptions with runaway current plateau formation in JET and implications for ITER
journal, May 2011

Disruption mitigation by massive gas injection in JET
journal, November 2011

Disruption scenarios, their mitigation and operation window in ITER
journal, March 2007

Gas jet disruption mitigation studies on Alcator C-Mod
journal, October 2006

Disruption mitigation on Alcator C-Mod using high-pressure gas injection: Experiments and modeling toward ITER
journal, June 2007

Pedestal conditions for small ELM regimes in tokamaks
journal, April 2006

Magnetohydrodynamic stability of tokamak edge plasmas
journal, July 1998

H-mode pedestal characteristics in ITER shape discharges on DIII-D
journal, March 1999