supported by the fusion energy sciences tokamak disruption

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1 2021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21) Supported by the U.S. Department of Energy Office of Science Fusion Energy Sciences Supported by US DOE grants DE-SC0016614, DE-SC0018623, DE-FG02-99ER54524 and contract DE-AC02-09CH11466 MAST-U ASDEX-U S.A. Sabbagh 1 , J.W. Berkery 1 , Y.S. Park 1 , J.M. Bialek 1 , J. Butt 1 , Y. Jiang 1 , V. Klevarova 1 , J.D. Riquezes 1 , J.G. Bak 2 , M.D. Boyer 3 , K. Erickson 3 , A.H. Glasser 4 , C. Ham 5 , S.H. Hahn 2 , J. Kim 2 , A. Kirk 5 , J. Ko 2 , W.H. Ko 2 , L. Kogan 5 , J.H. Lee 2 , M. Podesta 3 , D. Ryan 5 , A. Thornton 5 , S.W. Yoon 2 , Z.R. Wang 3 V4 1 Department of Applied Physics, Columbia University, New York, NY 2 Korea Institute of Fusion Energy, Daejeon, Republic of Korea 3 Princeton Plasma Physics Laboratory, Princeton, NJ 4 Fusion Theory and Computation, Inc., Kingston, WA 5 Culham Centre for Fusion Energy, UKAEA, Abingdon, UK Tokamak Disruption Event Characterization and Forecasting Research and Progress on Expansion to Real - Time Application 2021 IAEA-PPPL Workshop: Theory/Sim of Disruptions 23 July 2021 Virtual Meeting

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12021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Supported by theU.S. Department of Energy Office of ScienceFusion Energy Sciences

Supported by US DOE grants DE-SC0016614, DE-SC0018623, DE-FG02-99ER54524

and contract DE-AC02-09CH11466

MAST-U

ASDEX-U

S.A. Sabbagh1, J.W. Berkery1, Y.S. Park1, J.M. Bialek1, J. Butt1, Y.

Jiang1, V. Klevarova1, J.D. Riquezes1, J.G. Bak2, M.D. Boyer3, K.

Erickson3, A.H. Glasser4, C. Ham5, S.H. Hahn2, J. Kim2, A. Kirk5, J. Ko2,

W.H. Ko2, L. Kogan5, J.H. Lee2, M. Podesta3, D. Ryan5, A. Thornton5,

S.W. Yoon2, Z.R. Wang3

V4

1Department of Applied Physics, Columbia University, New York, NY2Korea Institute of Fusion Energy, Daejeon, Republic of Korea

3Princeton Plasma Physics Laboratory, Princeton, NJ4Fusion Theory and Computation, Inc., Kingston, WA

5Culham Centre for Fusion Energy, UKAEA, Abingdon, UK

Tokamak Disruption Event Characterization and Forecasting

Research and Progress on Expansion to Real-Time Application

2021 IAEA-PPPL Workshop:

Theory/Sim of Disruptions

23 July 2021

Virtual Meeting

22021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Disruption prediction and avoidance research progressing

for ITER and future tokamaks – expanding to real-time

Motivation: Disruption prediction/avoidance is a critical need

Why? A disruption stops plasma operation, might cause device damage

A highest priority DOE FES (Tier 1) initiative - present “grand challenge”

in tokamak stability research:

• Can be done! (JET: < 4% disruptions with carbon wall)

• ITER disruption allowance: < 1 - 2% (energy + E&M loads); << 1% (runaways)

Outline

Disruption Event Characterization and Forecasting (DECAF) analysis

• Disruption event chains, early forecasting, brief results, continued development

Recent focus on real-time DECAF design and implementation on KSTAR

Expanded physics analysis supporting DECAF

• e.g. KSTAR high bN, D’ analysis, high to ~100% non-inductive CD transport

analysis

32021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

DECAF is a physics-based approach to disruption event

understanding / forecasting to enable disruption avoidance

Physical event modules encapsulate disruption chain events

Continued development

focuses on improving

these modules

Structure eases parallel

development incl. real-time

KEY: Offline and real-time analysis INTEGRATED

The SAME researchers

that oversee the offline

code/analysis are

responsible for real-time

code specifications

Main data

structure

Code control

workbooksDensity Limits

Confinement

Stability

Tokamak

dynamics

Power/current

handling

Technical issues

Physical event

modules

Output

processing

Tokamak

databases

DECAF

database

42021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

DECAF is structured to ease parallel development of

disruption characterization, event criteria, and forecasting

Physical event modules encapsulate disruption chain events. Examples:

Main data

structure

Code control

workbooksDensity Limits

Confinement

Stability

Tokamak

dynamics

Power/current

handling

Technical issues

Physical event

modules

Output

processing

Tokamak

databases

DECAF

database

VDE

DIS

IPR

HLB

GWL

IPB

LON

PRP

LTM

RWMRKM

MHD BIF

LOQ

WPC

Greenwald limit

Island power balance

Low density

H-L back-transition

MHD

Bifurcation

Locked modeVDE

Pressure peaking

Low qRWM and

Kinetic RWM

forecastingNot at requested Ip

Wall proximity control

Disruption

52021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

DECAF provides an early disruption forecast - on transport

timescales – giving potential for disruption avoidance

DECAF event chain reveals physics Rotating MHD slows, bifurcates, and locks

126962

Disruption forecast level

DECAF

MHD

events

MHD-n1 PRP DISIPR WPC VDE

(0.490s)

BIF-n1 LTM-n1

(+.068s) (+.073s) (+.073s) (+.077s) (+.080s)(+.005s) (+.045s)

DECAF

event chain

Then, plasma has an H-L back-transition (pressure peaking warning PRP) before DIS

Important: Early warning occurs in apparently SAFE region of operating space!

NSTX

Safe

n

1

2

3

62021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

DECAF MHD events also produce early disruption

warnings for KSTAR; aim to compute in real-timeDECAF automated MHD objects DECAF “heat map” (for MHD)

Mode locking at reduced plasma rotation

Key notables of MHD warning

“Safe”/“unsafe” MHD periods

Early disruption warning (300

ms) on transport timescale

MHD warning level

Safe

KSTAR16299

MHD-n1

MHD-n2

Very low frequency mode

Plasma rotation profileand dynamics

High amplitude mode

}

Decreasing bN

co

nditio

n

time (s)

fre

que

ncy (

kH

z)

wa

rnin

g le

ve

l

n

1

2

3

72021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Continued development of DECAF builds from an

extrapolable approach with strong initial success

Fully automated, physics-based analysis of existing tokamak databases from multiple devices

Analysis of all plasma states, continuous and asynchronous events, continuous “warning level” determination

“Safe”: events indicating steady operation (e.g. determination of L-mode,

H-mode, steady ELMing, etc.)

“Proximity”: expected paths to “critical” events

“Critical”: event chains leading to disruption if no action taken

“Forecaster events” using models to provide the earliest possible indication of issues

High success found to date, determined quantitatively

> 91% true positive, ~ 8% false positive rate (~1e4 shots, ~1e6 samples)

Research continues focused on improving forecasting to needed accuracy (98%+ goal, w/low false positives),

LTMMHD HLB DIS

82021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Recent focus: implementation of real-time (r/t)

diagnostic hardware at KSTAR enabling DECAF

Implementation of real-time diagnostic capabilities

rtMHD system taking data; FPGA card real-time processing of FFTs with

programming for all 16 channels channels completed (W. Que)

rtVf system installed, data taken in 2020, Vf(R) profile measured with

temporary calibration; new system designed, to install 2021 (M. Podesta)

rtECE system (Te(R)) installed at KSTAR, accessible, on new Dolphin r/t

network (10x bandwidth of present RFM network)

rtECEI system (2D dTe) installed at KSTAR, accessible, on new Dolphin

network

rtMSE computer and interface in design (B pitch angle, dB) (F. Levinton)

DOE “Reach: Milestone (for KSTAR 2021 run campaign)

DEPARTE-2021-4R: Utilize first real-time DECAF events to actuate the

KSTAR shattered pellet injectors (SPI) for disruption mitigation

DECAF “LTM event forecaster” planned to be used for this demonstration

92021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Overall setup for KSTAR real-time diagnostic

integration and DECAF analysis for the PCS

All software development under GIT version control

Main Diagnostics RoomPCS Room

KSTAR Test Cell / ECE Screen Room

A-to-D

(192 ch)Expansion box connected

to main ECEI r/t computer

r/t ECEI and

r/t DECAF

development

computer

rtDECAF

Optical

isolation

(Dolphin)1G to KSTAR imaging data server & MDSPlus

r/t MHD

computer

rtDECAF

r/t ECE computer

(includes Te(R)

calibrations 73 ch)

r/t Vf computer

(includes profile

calibration 16 ch)

r/t MSE computer

(includes profile

calibration 25 ch)

KSTAR

PCS

RFM

r/t DECAF

development

computer

rtDECAF

1G to MDSPlus

RFM

RFM

1G to MDSPlus

RFM

RFM

RFM

Dolphin

Dolphin

Dolphin

1G to MDSPlus

1G to MDSPlus

1G to MDSPlus

Main Diagnostics Rm

= installed

Dolphin

network switch

102021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Real-time toroidal velocity diagnostic (rtVf) installation

completed on KSTAR (Oct. 29th), first light the next day!

A01

A16

B01

B16

No light

in B13

No light

in A03

26333

First Light! 32 channels

M. Podesta, J. Yoo (PPPL),

Y.S. Park (CU), WH. Ko (KFE) Initial real-time KSTAR Vf profile data taken 2020

112021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Real-time Vf profile shows very good agreement

with KSTAR CER system

122021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

KSTAR real-time ECE and ECEI data acquisition

hardware installed earlier this year (2021)

rtECE computer near heterodyne radiometer (76 channels)

rtECEI computer connected to diagnostic by PCIe expansion box and custom interface in test cell (2D: 192 channels!)

rtECEI

rtECE

rtECE

interface

H.K. Park, Adv. in Physics: X, 4:1, 1633956 (2019)

K.D. Lee, KFE

132021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

The first real-time DECAF module in KSTAR PCS

recently measured Te profile (1st time last week)

Te

(eV

)

First real-time ECE data (Te(R))

(red: real-time; black: off-line)

0 3 6 9 12 15

Te

(eV

)T

e(e

V)

Te

(eV

)

core

edge

t (s)

rtECE

rtECE

interface

Calibrated system, agrees with offline data acquisition

142021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

rtECEI DAQ system installed in the KSTAR test cell

rtECEIcomputer located in the ECE rack (diagnostics room)

LEMO cables installed for buffer chassis hook-up

Dolphin cable run from ECEI DAQ in test cell to rtECEIcomputer

Buffer chassis (192 channels) PCIe expansion chassis

In ECEI DAQ room (test cell) In ECEI DAQ room (test cell)

152021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

The first real-time ECEI data on KSTAR was

recently taken as well (1st time last week)

3 of 192 channels shown

rtECEI

Te

sig

nal

(V)

Te

sig

nal

(V)

Te

sig

nal

(V)

0 2 4 6 8 10t (s)

162021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

New DECAF edge localized mode event created to

start examining correlations to other MHD

DECAF ELM event

Presently determines

ELM triggering times,

along with frequency and

relative amplitude

Algorithm compatible with real-time use

Distinguishes true “ELMs” from other events (global MHD, etc.) that generate Dalight

Magenta dashed lines at

t = 0.6s is a global mode

ELM

KSTAR

NSTX

16325

Da

(arb

)

t (s)

Da

(arb

)

0 2 4 6 8 10 12 14

1.0

2.0

3.0

4.0

0.0

0.5

1.0

1.5

2.0

0.013984

0.1 0.2 0.3 0.4 0.5 0.6 t (s)0.7

172021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Te profile provides critical addition to Da ELM detection by determining radial extent of perturbation – useful for real-time

Te ↓ in core

Te ↓ in edge

GLOBAL decrease

• Global Te drop, Slow Neutrons (&

Wtot) exhibit catastrophic drop D⍺ info now to be passed to

other DECAF events• Low frequency, large-amplitude low-f

mode • Strong RWM sensor (BR, Bp) signal

increase• Apparent RWM, not ELM

Te profile evolution

J. Butt (this meeting)

NSTX

182021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Real-time MHD system taking data on KSTAR to be

used for real-time DECAF application in 2021

Real-time MHD analysis computer installed at KFE

Part of plasma control system

System FGPA chip now

computing FFTs in real-time

Offline Magnetic probe spectrogram analysis

DECAF analysis of real-time signals

Fre

qu

en

cy (

kH

z)

192021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Simple island rotation dynamics model used to

forecast the bifurcation point to signal disruption

Cylindrical, rigid body model

Possible model of drag for both a “slip” and a “no slip” condition:

At very low angular speed, mode can

reach a stable steady state,

observed in KSTAR

First real-time model, assume“no slip” condition

𝑇𝑚𝑜𝑑𝑒 =𝑘2Ω

1 + 𝑘3Ω2

R. Fitzpatrick et al., Nucl. Fusion 33 (1993) 1049

𝑑 𝐼Ω

𝑑𝑡= 𝑇𝑎𝑢𝑥 −

𝑘2Ω

1 + 𝑘3Ω2 −

𝐼Ω

𝜏2𝐷

Ω0

𝑘2 = 0

Bifurcation

𝑇𝑚𝑜𝑑𝑒 =𝑘1Ω

J. Riquezes (this meeting)

202021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

New locked mode (LTM) forecaster “measures” key

parameters, provides early warning, high success

Disruption forecasted when mode freq. < 0.5x computed inflection freq.

13 KSTAR shots from 2020 analysed, 100% success rate; 1.5s warning!

KSTAR 23874

KSTAR 25829

Safe plasma discharge Disrupting plasma discharge

forecasted critical frequency

forecasted critical frequency

mode frequencymode frequency 1.5s

212021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

DECAF is fueled by coordinated research that

continues to validate/develop physics models, e.g.:

Resistive MHD

Detection / forecasting: available magnetic diagnostics, plasma rotation

Forecasting: examination of MRE start with D’ evaluation

Density limits

Detection: rad. power, global empirical limit

Forecasting: examination of rad. island power balance model

Global MHD

Detection: available magnetic diagnostics, plasma rotation, equilibrium

Forecasting: Kinetic MHD model has high success in NSTX, DIII-D

Physics analysis / experiments to build DECAF models

Interpretive and “predict-first” TRANSP analysis of KSTAR long-pulse,

high beta plasmas with high non-inductive fraction

222021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

16325

Classical tearing stability index, D′, computed at q = 2 surface using outer layer

solutions

At higher q95, D′ is mostly positive predicting unstable classical tearing mode

• Indicates neoclassical effects, additional physics needed to reproduce XP

• KEY POINT: Conclusions regarding D’ evolution can be made!

• Recent paper with MRE evaluation Y.S. Park, et al., NF 60 (2020) 056007

Tearing mode classical D’ stability examined in

KSTAR plasmas (supports future DECAF models)

Experimentally

2/1 stable

*Resistive DCON Δ′

bN ~ 2

Ideal DCON dW

bN ~ 2

16325

*A.H. Glasser PoP (2016)

232021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Tearing mode classical D’ and ideal stability

sensitivity to models also studied in KSTAR

-50

-25

0

25

50

75

100

0 2 4 6 8 10 12 14

Δ’(

q =

2)

Times (s)

-4

-2

0

2

4

6

8

-δW

n=

1n

o-w

all

unstable

stable

1E-08

1E-07

1E-06

1E-05

1E-04

1E-03

1E-02

1E-01

Co

nve

rge

nce

err

or

-50

-25

0

25

50

75

100

0 2 4 6 8 10 12 14

Δ’(

q =

2)

Times (s)

-4

-2

0

2

4

6

8

-δW

n=

1n

o-w

all

1E-08

1E-07

1E-06

1E-05

1E-04

1E-03

1E-02

1E-01

Co

nve

rge

nce

err

or5th order of P’ 5th order of ff’

2 constraints 8 free parameters

Ideal stability Ideal stability

resistive stability resistive stability

16325 16325

unstable

stable

unstable

stable

unstable

stable

qmin ~ 1.5 qmin ~ 1.5

Y. Jiang (submitted to Nucl. Fusion)

242021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

<TRANSP>

bN = 3.4

fNI = 96%

PNBI = 6.5 MW

Predictive TRANSP analysis shows KSTAR design

target 𝜷𝑵~5 can be approached with 𝒇𝑵𝑰~100%

Up to 75% NICF already reached in similar plasmas

By altering 𝐼𝑃 and 𝐵𝑇values, 𝛽𝑁 > 4 , up to KSTAR design target 5can be achieved with 100% NICF

n=1 no-wall limit

n=1 with-wall limit

βN/li=6 βN/li=5𝐁𝐓=1.5T Predicted

𝐁𝐓=2.0T

𝐁𝐓=1.7T

Interpretive

“Predict-first” analysis used to design high-β , 100% non-inductive current

fraction (NICF) experiments for present KSTAR run campaign

252021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

DECAF application and research for disruption

prediction and avoidance expanding to real-time

Multi-faceted, integrated approach to disruption prediction and avoidance with several key characteristics

Physics-based approach yields key understanding of evolution toward

disruptions: confident extrapolation of forecasting, avoidance by control

Full multi-machine databases used (full databases needed!)

Open to all methods of data analysis (physics, machine learning, etc.)

DECAF analysis produces early warning disruption forecasts

Sufficiently early for potential disruption avoidance by profile control

Significant physics support efforts from multiple devices

KSTAR D’ analysis, high to ~100% non-inductive CD transport analysis

Implementing real-time DECAF analysis in KSTAR (4 out of 5 new real-time diagnostic data acquisition systems installed)

See A. Piccione poster (this meeting)

262021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

Supporting slides

272021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

A database of high-non-inductive fraction plasmas is

important for disruption forecasting ; NICF ~ 75% in KSTAR

18492

16498

18476

1632516295

TRANSP analysis

of experimental

plasmas

Non-inductive

fraction

Beam-driven

Bootstrap

Non-inductive

fraction is key for

stable high beta

steady state

operationVolume average electron density (m-3)

282021 IAEA-PPPL TSDW: Tokamak Disruption Event Characterization and Forecasting Research - Real-Time Expansion (S.A. Sabbagh, et al. 7/23/21)

“Predict-first” KSTAR TRANSP analysis shows

expected high performance plasmas at > 80% NICF

High non-inductive current fraction predicted for 6.5, 7.5, 8.5 MW NBI

The bN ranges from 3.0 – 3.5; based on KSTAR plasmas with NICF ~70%

Aim to generate a significant database of long pulse, high NICF plasmas in 2021 KSTAR run for disruption prediction studies

Predicted high non-inductive current fraction (NICF) current profiles

81.5% NICF 93% NICF 101% NICF