Don Spong (ORNL), ZhihongLin (UCI), Sam Taimourzadeh (UCI ...€¦ · Don Spong (ORNL), ZhihongLin...

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Don Spong (ORNL), Zhihong Lin (UCI), Sam Taimourzadeh (UCI), and the ISEP Team ISEP Introduction ISEP computational models Long-time simulation of energetic particle instabilities Conclusions and future work ISEP Verification and Validation Activities GTC First Ø -principles, multi-physics, global gyrokinetic particle-in-cell (PIC) model with applications to microturbulence, meso-scale EP instabilities, MHD modes, RF (radio-frequency) heating and neoclassical transport Adapted to peta Ø -scale and emerging exascale platforms MPI, OpenMP and GPU parallelism Ø GYRO Comprehensive continuum (Eulerian) electromagnetic global Ø δf gyrokinetic model Includes full physics features needed to realistically simulate Ø turbulence and transport in experimental tokamak discharges FAR3D/TAEFL High fidelity reduced stability model using Landau Ø -fluid closures to include resonant drives and Padi approximations to include finite gyro-radius effects Time evolution and direct Ø eigensolver options Collaborating models GEM Ø – gyrokinetic ẟf PIC EUTERPE Ø – global, electromagnetic gyrokinetic PIC ORB5 Ø – linear/nonlinear gyrokinetic PIC MEGA Ø – kinetic/MHD hybrid M3D Ø -K - kinetic/MHD hybrid NOVA Ø -K – linear hybrid kinetic/MHD Motivations EP ( Ø Energetic Particle) confinement is a critical issue for self-heated ignition experiments such as ITER – ignition requires good EP confinement EPs can Ø excite mesoscale EP instabilities => drive large EP transport. These can degrade overall plasma confinement and threaten the Ø integrity of the wall and plasma-facing components EPs Ø => significant fraction of the plasma energy density in ITER. EPs can influence microturbulence responsible for turbulent transport of thermal plasmas and macroscopic magnetohydrodynamic (MHD) modes potentially leading to disruptions Ø Ignition regime plasma confinement with α-particle heating: one of the most uncertain issues for extrapolating from existing devices to ITER. Objectives to improve physics understanding of EP confinement and EP Ø interactions with burning thermal plasmas through exa-scale simulations To develop a comprehensive predictive capability for EP physics Ø To deliver an EP module incorporating both first Ø -principles simulation models and high fidelity reduced transport models to the fusion whole device modeling (WDM) project. (d) (e) (f) (g) (h) (i) 1.2 1.4 1.6 1.8 2.0 2.2 -0.5 0.0 0.5 1.2 1.4 1.6 1.8 2.0 2.2 0.5 0.0 0.5 - 1.2 1.4 1.6 1.8 2.0 2.2 0.5 0.0 0.5 - Long term intermittency example: multi-mode nonlinear gyrofluid simulation of #142111 for fixed q-profile with source balanced against losses for 10 4 Alfvén times (~ 3 msec) Frequency spectrogram showing n = 2 and 3 modes n = 3 RSAE n = 2 TAE DIII-D #142111 spectrogram Intermittent predator/prey phenomena: coherent structure alternating with zonal flow sheared convective cells t=3600 t=2000 t=5050 t=5300 t=6400 t=7600 t=8600 Verification and Validation ISEP and the previous GSEP projects have developed close Ø connections with fusion experiments, such as DIII-D, for successful V&V activities In addition to the primary ISEP models, we have engaged with Ø outside EP modeling codes Recent linear stability verification will be extended to the Ø nonlinear regime Long -term nonlinear simulations Mutiple Ø AE modes have been followed for 10,000 Alfvén times Extension to recent DIII Ø -D transport analysis case Connection with critical gradient modeling Ø Source/sink balancing models will be further Ø deveolped time ρ n fast Zonal flow growth and collapse cycles D. Spong, Plasma and Fusion Research, Vol. 9, 3403077 (2014) Previous GSEP verification and validation activity Directed toward the simulation of RSAE modes in the DIII Ø -D tokamak (discharge #142111) with time-evolving frequencies 3 codes: GTC, GYRO, and TAEFL Ø – linear analysis D. A. Spong, E. M. Bass, W. Deng, W. W. Ø Heidbrink, Z. Lin, B. Tobias, M. A. Van Zeeland, M. E. Austin, C. W. Domier, N. C. Luhmann, Jr., "Verification and validation of linear gyrokinetic simulation of Alfven eigenmodes in the DIII-D tokamak," Phys. Plasmas Vol. 19 (2012) 082511-1. Current ISEP verification and validation activity Directed toward the simulation of RSAE and TAE modes in the DIII Ø -D tokamak (discharge #159243 which featured comprehensive stability and fast ion transport diagnostics C. Collins, W. Ø Heidbrink, M. Podesta`, R. White, G. Kramer, D. Pace, et al., “Phase-space dependent critical gradient behavior of fast-ion transport due to alfv ́en eigenmodes,” Nuclear Fusion, vol. 57, no. 8, p. 086 005, 2017. 8 codes: GTC, GYRO, FAR3D, GEM, EUTERPE, ORB5, MEGA, NOVA Ø Both linear and nonlinear simulations are in progress Ø Measured mode Structure for q min = 3.22 Frequency/growth rate variation with q min among the 3 models GTC Predicted 2D mode structures GYRO TAEFL q min = 3.3 q min = 3.22 q min = 3.16 Profiles and plasma shape Experimental spectrograms and amplitude variation RSAE mode structure comparison for n = 4 Frequency/growth rate vs. toroidal mode number comparison among the 8 models for data at t = 805 msec Nonlinear Alfvénic instability simulation is important for understanding EP transport effects and heat loads on plasma-facing components (PFC) Critical gradient (time average effect): EP profiles evolve to be near marginal Ø stability => stiff transport regime => profiles don’t change with increasing power Long Ø -time nonlinear effects: variation, intermittency about critical gradient point => instantaneous losses exceed time average and can cause PFC damage Intermittency in EP density profile Energetic particle instabilities – V&V challenges The EP Ø -driven Alfvén spectrum typically includes many unstable modes Whic Ø h mode dominates is model dependent and sensitive to profiles Ø A variety of different EP stability models have been developed (see below) The Ø most important profiles determining AE stability (n fast , E fast , q-profile) are not measured directly, but inferred from reconstruction or modeling Fast ion profiles are “sculpted Ø -out” over time by AE instabilities

Transcript of Don Spong (ORNL), ZhihongLin (UCI), Sam Taimourzadeh (UCI ...€¦ · Don Spong (ORNL), ZhihongLin...

Page 1: Don Spong (ORNL), ZhihongLin (UCI), Sam Taimourzadeh (UCI ...€¦ · Don Spong (ORNL), ZhihongLin (UCI), Sam Taimourzadeh (UCI), and the ISEP Team ISEP Introduction ISEP computational

Don Spong (ORNL), Zhihong Lin (UCI), Sam Taimourzadeh (UCI), and the ISEP Team

ISEP Introduction

ISEP computational models

Long-time simulation of energetic particle instabilities

Conclusions and future work

ISEP Verification and Validation Activities

GTC•FirstØ -principles, multi-physics, global gyrokinetic particle-in-cell

(PIC) model with applications to microturbulence, meso-scale

EP instabilities, MHD modes, RF (radio-frequency) heating

and neoclassical transport

Adapted to petaØ -scale and emerging exascale platforms

MPI, OpenMP and GPU parallelismØ

GYRO•Comprehensive continuum (Eulerian) electromagnetic global Øδf gyrokinetic model

Includes full physics features needed to realistically simulate Øturbulence and transport in experimental tokamak discharges

FAR3D/TAEFL•High fidelity reduced stability model using LandauØ -fluid

closures to include resonant drives and Padi approximations to

include finite gyro-radius effects

Time evolution and direct Ø eigensolver options

Collaborating models•GEM Ø – gyrokinetic ẟf PIC

EUTERPE Ø – global, electromagnetic gyrokinetic PIC

ORB5 Ø – linear/nonlinear gyrokinetic PIC

MEGA Ø – kinetic/MHD hybrid

M3DØ -K - kinetic/MHD hybrid

NOVAØ -K – linear hybrid kinetic/MHD

Motivations•EP (Ø Energetic Particle) confinement is a critical issue for self-heated

ignition experiments such as ITER – ignition requires good EP

confinement

EPs can Ø excite mesoscale EP instabilities => drive large EP transport.

These can degrade overall plasma confinement and threaten the Øintegrity of the wall and plasma-facing components

EPs Ø => significant fraction of the plasma energy density in ITER. EPs

can influence microturbulence responsible for turbulent transport of

thermal plasmas and macroscopic magnetohydrodynamic (MHD)

modes potentially leading to disruptions

Ø Ignition regime plasma confinement with α-particle heating: one of the

most uncertain issues for extrapolating from existing devices to ITER.

Objectives•to improve physics understanding of EP confinement and EP Øinteractions with burning thermal plasmas through exa-scale

simulations

To develop a comprehensive predictive capability for EP physics ØTo deliver an EP module incorporating both firstØ -principles simulation

models and high fidelity reduced transport models to the fusion whole

device modeling (WDM) project.

(a)

(b)

(c)

(d)

(e)

(f)

(g)

(h)

(i)

qmin = 3.30 qmin = 3.22 qmin = 3.16

1.2 1.4 1.6 1.8 2.0 2.2

-0.5

0.0

0.5

1.2 1.4 1.6 1.8 2.0 2.2

0.5

0.0

0.5

-

1.2 1.4 1.6 1.8 2.0 2.2

0.5

0.0

0.5

-

Long term intermittency example: multi-mode nonlinear gyrofluid simulation of #142111 for

fixed q-profile with source balanced against losses for 104 Alfvén times (~ 3 msec)

Frequency spectrogram showing n = 2 and 3 modes

n = 3 RSAEn = 2 TAE

DIII-D #142111 spectrogram

Intermittent predator/prey phenomena: coherent structure alternating with zonal flow sheared convective cells

t=3600t=2000 t=5050 t=5300 t=6400 t=7600 t=8600

Verification and Validation•ISEP and the previous GSEP projects have developed close Øconnections with fusion experiments, such as DIII-D, for

successful V&V activities

In addition to the primary ISEP models, we have engaged with Øoutside EP modeling codes

Recent linear stability verification will be extended to the Ønonlinear regime

Long• -term nonlinear simulationsMutipleØ AE modes have been followed for 10,000 Alfvén times

Extension to recent DIIIØ -D transport analysis case

Connection with critical gradient modelingØSource/sink balancing models will be further Ø deveolped

timeρ

nfast

Zonal flow growth and collapse cycles

D. Spong, Plasma and Fusion Research, Vol. 9, 3403077 (2014)

Previous GSEP verification and validation activity•Directed toward the simulation of RSAE modes in the DIIIØ -D tokamak

(discharge #142111) with time-evolving frequencies

3 codes: GTC, GYRO, and TAEFL Ø – linear analysisD. A. Spong, E. M. Bass, W. Deng, W. W. Ø Heidbrink, Z. Lin, B. Tobias, M. A. Van Zeeland, M. E.

Austin, C. W. Domier, N. C. Luhmann, Jr., "Verification and validation of linear gyrokinetic simulation

of Alfven eigenmodes in the DIII-D tokamak," Phys. Plasmas Vol. 19 (2012) 082511-1.

Current ISEP verification and validation activity•Directed toward the simulation of RSAE and TAE modes in the DIIIØ -D tokamak (discharge

#159243 which featured comprehensive stability and fast ion transport diagnosticsC. Collins, W. Ø Heidbrink, M. Podesta`, R. White, G. Kramer, D. Pace, et al., “Phase-space dependent critical gradient

behavior of fast-ion transport due to alfv ́en eigenmodes,” Nuclear Fusion, vol. 57, no. 8, p. 086 005, 2017.

8 codes: GTC, GYRO, FAR3D, GEM, EUTERPE, ORB5, MEGA, NOVAØBoth linear and nonlinear simulations are in progressØ

Measured mode

Structure for qmin = 3.22

Frequency/growth rate variation with qmin

among the 3 models

GTC

Predicted 2D mode structures

GYRO

TAEFL

qmin = 3.3 qmin = 3.22 qmin = 3.16

Profiles and plasma shapeExperimental spectrograms and amplitude variation

RSAE mode structure comparison for n = 4

Frequency/growth rate vs. toroidal mode number

comparison among the 8 models for data at t = 805

msec

Nonlinear • Alfvénic instability simulation is important for understanding EP transport effects and heat loads on plasma-facing components (PFC)

Critical gradient (time average effect): EP profiles evolve to be near marginal Østability => stiff transport regime => profiles don’t change with increasing power

LongØ -time nonlinear effects: variation, intermittency about critical gradient point

=> instantaneous losses exceed time average and can cause PFC damage

Intermittency in EP density profile

Energetic particle instabilities – V&V challengesThe EPØ -driven Alfvén spectrum typically includes many unstable modes

WhicØ h mode dominates is model dependent and sensitive to profiles

Ø A variety of different EP stability models have been developed (see below)

TheØ most important profiles determining AE stability (nfast, Efast, q-profile)

are not measured directly, but inferred from reconstruction or modeling

Fast ion profiles are “sculptedØ -out” over time by AE instabilities