A multivariate analysis of disruption precursors on JET and AUG

Similar documents
Testing for Chaos in Type-I ELM Dynamics on JET with the ILW. Fabio Pisano

Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform

EX/4-2: Active Control of Type-I Edge Localized Modes with n = 1 and n = 2 fields on JET

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET

EX8/3 22nd IAEA Fusion Energy Conference Geneva

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET (Joint European Torus)

Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography

Experimental studies of ITER demonstration discharges

Global stabilization effect of Shafranov shift on the edge pedestal plasmas in JET and JT-60U

MHD Induced Fast-Ion Losses in ASDEX Upgrade

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas

A Detailed Analysis of Geodesic Least Squares Regression and Its Application to Edge-Localized Modes in Fusion Plasmas

Multi-Machine Experiments to Study the Parametric Dependences of Momentum Transport

New developments in JET gamma emission tomography

Recent progress towards a functional model for filamentary SOL transport

Divertor configuration with two nearby poloidal field nulls: modelling and experiments for EAST and JET tokamaks

MHD limits and plasma response in high beta hybrid operations in ASDEX Upgrade

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code

Turbulent Transport Analysis of JET H-mode and Hybrid Plasmas using QuaLiKiz, TGLF and GLF23

Progress in understanding W control using ICRH in the JET-ILW tokamak

Power Balance Analysis of Wendelstein 7-X Plasmas Using Profile Diagnostics

GA A25410 DISRUPTION CHARACTERIZATION AND DATABASE ACTIVITIES FOR ITER

The performance of improved H-modes at ASDEX Upgrade and projection to ITER

Improved Confinement in JET High b Plasmas with an ITER-Like Wall

INTERNATIONAL ATOMIC ENERGY AGENCY 22 nd IAEA Fusion Energy Conference Geneva, Switzerland, October 2008

Divertor Power Handling Assessment for Baseline Scenario Operation in JET in Preparation for the ILW

Improved EDGE2D-EIRENE Simulations of JET ITER-like Wall L-mode Discharges Utilising Poloidal VUV/visible Spectral Emission Profiles

(Motivation) Reactor tokamaks have to run without disruptions

Magnetic Flux Surface Measurements at Wendelstein 7-X

Confinement and edge studies towards low ρ* and ν* at JET

ITR/P1-19 Tokamak Experiments to Study the Parametric Dependences of Momentum Transport

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET

INTERNATIONAL ATOMIC ENERGY AGENCY 22 nd IAEA Fusion Energy Conference Geneva, Switzerland, October 2008

Upgrade of the Present JET Shape and Vertical Stability Controller

Characterization and Forecasting of Unstable Resistive Wall Modes in NSTX and NSTX-U *

STUDY OF ADVANCED TOKAMAK PERFORMANCE USING THE INTERNATIONAL TOKAMAK PHYSICS ACTIVITY DATABASE

Energy Resolution of LaBr 3 (Ce) Gamma-Ray spectrometer for Fusion Plasma Studies on JET

Analysis of runaway beam suppression experiments in FTU

The emissivity of W coatings deposited on carbon materials for fusion applications

Experimental Evidence of Inward Momentum Pinch on JET and Comparison with Theory

Plasma Start-Up Results with EC Assisted Breakdown on FTU

Divertor Heat Load in ITER-Like Advanced Tokamak Scenarios on JET

covers these specific topics and this paper reports on significant progress made recently in these areas. For work on disruption avoidance, not discus

Implications of JET-ILW L-H Transition Studies for ITER

In situ wavelength calibration of the edge CXS spectrometers on JET

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén

Integrated Core-SOL-Divertor Modelling for ITER Including Impurity: Effect of Tungsten on Fusion Performance in H-mode and Hybrid Scenario

Power Exhaust on JET: An Overview of Dedicated Experiments

Influence of Impurity Seeding on ELM Behaviour and Edge Pedestal in ELMy H-Mode Discharges

Modelling of Carbon Erosion and Deposition in the Divertor of JET

Mitigation of ELMs and Disruptions by Pellet Injection

L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET

Onset of Tearing Modes in JET Advanced Scenarios

ADVANCES IN PREDICTIVE THERMO-MECHANICAL MODELLING FOR THE JET DIVERTOR EXPERIMENTAL INTERPRETATION, IMPROVED PROTECTION, AND RELIABLE OPERATION

Impact of Neon Injection on Electron Density Peaking in JET Hybrid Plasmas

Comparison of plasma breakdown with a carbon and ITER-like wall

Electron energy distribution function in the divertor region of the COMPASS tokamak during neutral beam injection heating

Comparative Transport Analysis of JET and JT-60U Discharges

Determination of q Profiles in JET by Consistency of Motional Stark Effect and MHD Mode Localization

INTERNATIONAL ATOMIC ENERGY AGENCY 21 st IAEA Fusion Energy Conference Chengdu, China, October 2006

TSC modelling of major disruption and VDE events in NSTX and ASDEX- Upgrade and predictions for ITER

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions

Statistical Validation of Predictive TRANSP Simulations of Baseline Discharges in Preparation for Extrapolation to JET D-T

Securing High β N JT-60SA Operational Space by MHD Stability and Active Control Modelling

Plasma formation in MAST by using the double null merging technique

Full Wave Propagation Modelling in View to Integrated ICRH Wave Coupling/RF Sheaths Modelling

The role of ELM s and inter-elm phases in the transport of heavy impurities in JET

Understanding Confinement in Advanced Inductive Scenario Plasmas Dependence on Gyroradius and Rotation

Temporal Evolution of Temperature and Argon Impurity Density Profiles Observed by X-ray Imaging Spectrometer Measurements at Wendelstein 7-X

ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER

Introduction to Fusion Physics

Role of Magnetic Configuration and Heating Power in ITB Formation in JET.

Spatio-temporal investigations on the triggering of pellet induced ELMs

L-mode filament characteristics on MAST as a function of plasma current measured using visible imaging

Application of the ECRH radiation for plasma diagnostics in Wendelstein 7-X

Optimization of Plasma Initiation Scenarios in JT-60SA

Flux-driven multi-channel simulations with the quasilinear gyrokinetic tokamak transport model QuaLiKiz

Comparison of plasma breakdown with a carbon and ITER-like wall

Evidence for enhanced main chamber wall plasma loads in JET ITER-like Wall at high radiated fraction

Internal Transport Barrier Triggering by Rational Magnetic Flux Surfaces in Tokamaks

Modelling of pulsed and steady-state DEMO scenarios

GA A26684 DISRUPTION, HALO CURRENT AND RAPID SHUTDOWN DATABASE ACTIVITIES FOR ITER

Advanced Ion Beam Calorimetry for the Test Facility ELISE

Tandem Collimators System

Non-linear modeling of the Edge Localized Mode control by Resonant Magnetic Perturbations in ASDEX Upgrade

Radiative type-iii ELMy H-mode in all-tungsten ASDEX Upgrade

Multiscale modelling of sheath physics in edge transport codes

Active Control of Type-I Edge Localized Modes with n=1 and n=2 fields on JET

RFP helical equilibria reconstruction with V3FIT-VMEC

DIVIMP simulation of W transport in the SOL of JET H-mode plasmas

Development and Validation of a Predictive Model for the Pedestal Height (EPED1)

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST

NumKin, Strasbourg, October 17 th, 2016

Ion Cyclotron Resonance Heating for tungsten control in various JET H-mode scenarios

II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas. D. Reiter

Comparison of theory-based and semi-empirical transport modelling in JET plasmas with ITBs

Simulation of PHA Soft X-Ray Spectra Expected from W7-X

Modelling of Frequency Sweeping with the HAGIS code

The H-mode pedestal structure and its role on confinement in JET with a carbon and metal wall

Transcription:

A multivariate analysis of disruption precursors on JET and AUG G.Sias 1, R. Aledda 1, B. Cannas 1, R. S. Delogu 2, A. Fanni 1, A. Murari 2, A. Pau 1, the ASDEX Upgrade Team 3 and JET Contributors 4 1 Electrical and Electronic Engineering Dept. - University of Cagliari, Cagliari, Italy 2 Consorzio RFX (CNR, ENEA, INFN, University of Padova, Acciaierie Venete SpA), Corso Stati Uniti 4, 35127 Padova, Italy 3 Max-Planck-Institüt für Plasmaphysik - EURATOM Association, Garching, Germany 4 EUROfusion Consortium, JET, Culham Science Centre, Abingdon, OX14 3DB, UK

Comparative multivariate analysis The aim of the work is to perform a disruption predictor both for JET and AUG by combining the prediction capability of a set of precursors in common between the two machines. The prediction capability of the signals reported in the following has been investigated. Acronym q95 LM Pradtot Pfrac Vloop ne_fr li dwmhd/dt Zcc signal Safety factor at 95% of poloidal flux Locked mode signal Total radiated power Total radiated power/ Total input Power Loop Voltage Line-averaged plasma density / Greenwald limit Internal inductance Time derivative of the total energy Vertical position of plasma centroid G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 2

Databases JET-ILW, 116 flat-top disruptions occurred between 2011-2012 Data set shots shot range training 77 81867-83340 test 39 83341-83698 AUG W-wall, 102 flat-top disruptions occurred between 2011-2014 Data set shots shot-range training 68 26903-28812 test 34 28813-30130 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 3

AUG pdf of signals Acronym q95 LM Pradtot Pfrac Vloop ne_fr li dwmhd/dt Zcc Disruption predictor N N N G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 4

JET pdf of signals Acronym q95 LM Pradtot Pfrac Vloop ne_fr li dwmhd/dt Zcc Disruption predictor y N N G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 5

Performance indexes Premature detection (PD): the fraction of disruptions triggered too much in advance Successful prediction (SP): the fraction of disruptions correctly predicted Tardy detection (TD): the fraction of disruptions triggered too late Missed alarm (MA): the fraction of disruptions predicted as safe. AUG PD SP TD t D -0.5 t D -0.002 t D MA Time [s] JET PD SP TD t D -1.5 t D -0.01 t D MA Time [s] G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 6

AUG signals as single predictors Training-set Signal Threshold PD SP TD MA LM [V] 0.15 0.13 0.74 0.01 0.12 Pradtot [MW] 12.0 0.12 0.75 0.09 0.04 Pfrac 1.60 0.16 0.84 0.00 0.00 Vloop [V] 2.61 0.06 0.66 0.06 0.22 li 1.52 0.00 0.79 0.04 0.16 Zcc [m] 0.085 0.10 0.16 0.03 0.71 Test-set Signal Threshold PD SP TD MA LM [V] 0.15 0.26 0.65 0.00 0.09 Pradtot [MW] 12.0 0.00 0.53 0.15 0.32 Pfrac 1.60 0.00 0.85 0.03 0.12 Vloop [V] 2.61 0.12 0.62 0.03 0.24 li 1.52 0.09 0.74 0.00 0.18 Zcc [m] 0.085 0.00 0.03 0.03 0.94 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 7

JET signals as single predictors Training-set Signal Threshold PD SP TD MA q95 3.80 0.19 0.36 0.01 0.43 LM [mt] 0.34 0.01 0.78 0.14 0.06 Pradtot [MW] 8.50 0.51 0.17 0.01 0.31 Pfrac 1.80 0.17 0.64 0.03 0.17 Vloop [V] 3.50 0.27 0.19 0.01 0.52 li 1.24 0.10 0.43 0.01 0.45 Zcc [m] 0.28 0.29 0.32 0.01 0.38 Test-set Signal Threshold PD SP TD MA q95 3.80 0.15 0.33 0.00 0.51 LM [mt] 0.34 0.03 0.69 0.13 0.15 Pradtot [MW] 8.50 0.54 0.23 0.00 0.23 Pfrac 1.80 0.23 0.59 0.05 0.13 Vloop [V] 3.50 0.23 0.21 0.03 0.54 li 1.24 0.08 0.41 0.00 0.51 Zcc [m] 0.28 0.18 0.23 0.08 0.51 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 8

Data fusion method for disruption prediction (*) For each signal a set of thresholds, which allows to achieve predefined PD rates, is identified A score (SC) is assigned to each threshold depending on the corresponding PD rate. At each time step during a discharge, the following steps are executed: 1. Each signal is compared with respect to its own thresholds and the corresponding score is assigned when a threshold is exceeded 2. The scores from the individual signals are totaled to form the aggregate score 3. A disruption warning is triggered when the aggregate score exceeds an optimized threshold value. The threshold values for each signal, their corresponding scores and the threshold on the aggregate score are optimized on the training set. *S.P. Gerhardt et al 2013 Nucl. Fusion 53 063021 doi:10.1088/0029-5515/53/6/063021 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 9

Data fusion method for disruption prediction AUG - Thresholds Signal PD=0.1 PD=0.06 PD=0.03 SC=2 SC=3 SC=5 LM [V] 0.16 0.2 0.27 Pradtot [MW] 13 14.5 17 Pfrac 2 2.3 2.6 Vloop [V] 2.59 2.61 2.9 li 1.45 1.465 1.48 Zcc [m] 0.085 0.0865 0.088 JET - Thresholds Signal PD=0.1 PD=0.06 PD=0.03 SC=1 SC=2 SC=4 LM [mt] 0.3100 0.3183 0.3300 Pradtot [MW] 22.66 22.96 23.95 Pfrac 2 2.2 4.7 Vloop [V] 5.7 6.1 6.97 Li 1.24 1.25 1.262 Zcc [m] 0.326 0.327 0.38 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 10

Data fusion method for disruption prediction TRAINING SETS: only variables in common between the two machines AUG JET PD SP TD MA ΔSP=SP-0.94 0.01 0.94 0.03 0.01 0.00 0.01 0.94 0.03 0.01 0.00 0.01 0.93 0.04 0.01-0.01 0.01 0.94 0.03 0.01 0.00 0.00 0.90 0.04 0.06-0.04 0.00 0.90 0.04 0.06-0.04 0.01 0.94 0.01 0.03 0.00 0.01 0.93 0.03 0.03-0.01 PD SP TD MA ΔSP=SP-0.79 0.06 0.79 0.04 0.10 0.00 0.04 0.82 0.04 0.10 0.03 0.06 0.78 0.04 0.12-0.01 0.06 0.79 0.04 0.10 0.00 0.04 0.77 0.04 0.16-0.02 0.06 0.79 0.04 0.10 0.00 0.06 0.48 0.01 0.44-0.31 0.04 0.82 0.04 0.10 0.03 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 11

Data fusion method for disruption prediction TEST SETS AUG PD SP TD MA 0.03 0.91 0.00 0.06 0.03 0.91 0.00 0.06 0.00 0.85 0.03 0.12 0.03 0.91 0.00 0.06 JET PD SP TD MA 0.08 0.74 0.03 0.15 0.05 0.77 0.03 0.15 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 12

Data fusion method for disruption prediction TEST set: 144 safe shots False alarm (FA): the fraction of safe shots predicted as disruptions Successful prediction (SP): the fraction of safe shot correctly predicted AUG FA SP 0.08 0.92 0.05 0.95 0.07 0.93 0.04 0.96 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 13

Locked Mode indicator Features extraction procedures in time and frequency domains: 1. Detrending and off-set removal of the normalized LM amplitude 2. σ of FFT on a 51.2ms sliding window N/2 i 3. f i abs FFT i on a 51.2ms sliding window 1) 2) 3) 4) G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 14

Locked Mode indicator Prediction performance: AUG Training set Signal Threshold PD SP TD MA LM_indicator 1.9E-04 0.06 0.84 0.04 0.06 LM 0.15 0.13 0.74 0.01 0.12 Test set PD SP TD MA 0.03 0.74 0.12 0.12 0.26 0.65 0.00 0.09 JET Training set Signal Threshold PD SP TD MA LM_indicator 1.1E-05 0.01 0.88 0.06 0.04 LM 0.34 0.01 0.78 0.14 0.06 Test set PD SP TD MA 0.05 0.77 0.10 0.08 0.03 0.69 0.13 0.15 G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 15

Comparison with the actual LM trigger AUG: the LM trigger on the considered data set achieves more than 0.50 of MA both on training and test sets JET: the LM trigger on the considered data set achieves SP=0.61 and SP=0.41 on training and test sets respectively. G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 16

Future work LM indicator will replace the LM signal as predictor input Others physical-based indicators will be added in order to improve the predictor performance For both machines, the database will be updated with most recent pulses (safe and disrupted) A performance statistical analysis taking into account disruption classes will be performed G. Sias et al. 1st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis Nice 1 st June Page 17