IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES

Similar documents
GA A23114 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier

Enhanced con nement discharges in DIII-D with neon and argon induced radiation

Experimental test of the neoclassical theory of poloidal rotation

GA A23403 GAS PUFF FUELED H MODE DISCHARGES WITH GOOD ENERGY CONFINEMENT ABOVE THE GREENWALD DENSITY LIMIT ON DIII D

ABSTRACT, POSTER LP1 12 THURSDAY 11/7/2001, APS DPP CONFERENCE, LONG BEACH. Recent Results from the Quiescent Double Barrier Regime on DIII-D

Integrated Heat Transport Simulation of High Ion Temperature Plasma of LHD

Integrated Particle Transport Simulation of NBI Plasmas in LHD )

Predicting the Rotation Profile in ITER

Effect of Ion Orbit Loss on Rotation and the Radial Electric Field in the DIII-D Tokamak

DIII D UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN DIII D QTYUIOP C.M. GREENFIELD. Presented by

Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling

1999 RESEARCH SUMMARY

Experimental analysis and predictive simulation of heat transport using TASK3D code

UEDGE Modeling of the Effect of Changes in the Private Flux Wall in DIII-D on Divertor Performance

Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0.

Physics of the detached radiative divertor regime in DIII-D

Plasma impurity composition in Alcator C-Mod tokamak.

Rotation Speed Differences of Impurity Species in the DIII-D Tokamak and Comparison with Neoclassical Theory

GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D

High fusion performance at high T i /T e in JET-ILW baseline plasmas with high NBI heating power and low gas puffing

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )

Light Impurity Transport Studies in Alcator C-Mod*

Nonlinear Gyrokinetic Simulations of Ion Turbulence in Impurity Seeded and High Density Toroidal Plasmas

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS

COMPARISON OF NEOCLASSICAL ROTATION THEORY WITH EXPERIMENT UNDER A VARIETY OF CONDITIONS IN DIII-D

Observation of Co- and Counter Rotation Produced by Lower Hybrid Waves in Alcator C-Mod*

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS

Time-dependent Modeling of Sustained Advanced Tokamak Scenarios

INTERNAL TRANSPORT BARRIERS WITH

THE DIII D PROGRAM THREE-YEAR PLAN

Characteristics of the H-mode H and Extrapolation to ITER

Abstract Submitted for the DPP99 Meeting of The American Physical Society

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

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

QTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL.

HFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION

Divertor Requirements and Performance in ITER

Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport*

GA A22636 RECENT H MODE DENSITY LIMIT EXPERIMENTS ON DIII D

Characteristics of Internal Transport Barrier in JT-60U Reversed Shear Plasmas

Low-collisionality density-peaking in GYRO simulations of C-Mod plasmas

Influence of Beta, Shape and Rotation on the H-mode Pedestal Height

Fusion Development Facility (FDF) Divertor Plans and Research Options

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model

Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas

Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options

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

Non-Solenoidal Plasma Startup in

H-mode performance and pedestal studies with enhanced particle control on Alcator C-Mod

GA A23736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT

Pedestals and Fluctuations in C-Mod Enhanced D α H-modes

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak

2017 US/EU Transport Task Force Workshop April 26 th 2017 Williamsburg, VA

Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas

On the ρ Scaling of Intrinsic Rotation in C-Mod Plasmas with Edge Transport Barriers

Particle Transport and Density Gradient Scale Lengths in the Edge Pedestal

Particle transport results from collisionality scans and perturbative experiments on DIII-D

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

1. Motivation power exhaust in JT-60SA tokamak. 2. Tool COREDIV code. 3. Operational scenarios of JT-60SA. 4. Results. 5.

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U

GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D

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

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

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device

Self-consistent modeling of ITER with BALDUR integrated predictive modeling code

Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas

Development of a Systematic, Self-consistent Algorithm for the K-DEMO Steady-state Operation Scenario

Results From Initial Snowflake Divertor Physics Studies on DIII-D

DIII D I. INTRODUCTION QTYUIOP

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport

Divertor Heat Flux Reduction and Detachment in NSTX

MHD Pedestal Paradigm (Conventional Wisdom)

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France

THE ADVANCED TOKAMAK DIVERTOR

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

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO

Development in DIII D Tokamak Hybrid Operation Scenarios

Fast ion physics in the C-2U advanced, beam-driven FRC

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code

Modelling plasma scenarios for MAST-Upgrade

EXC/P2-02. Experiments and Simulations of ITER-like Plasmas in Alcator C-Mod

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

Analysis of pedestal plasma transport

Alcator C-Mod. Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod

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

Control of plasma stored energy for burn control using DIII-D in-vessel coils

Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas

Plasma instability during ITBs formation with pellet injection in tokamak

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

Studies of Lower Hybrid Range of Frequencies Actuators in the ARC Device

Transcription:

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES J. Mandrekas, W.M. Stacey Georgia Institute of Technology M. Murakami, M.R. Wade ORNL G. L. Jackson General Atomics Presented at the 41 st APS DPP Meeting November 15 19, 1999 Seattle, WA

Abstract Submitted for the DPP99 Meeting of The American Physical Society Sorting Category: 5.1.1.2(Computation/) Impurity Analysis and Modeling of DIII-D Radiating Mantle Discharges 1 J. MANDREKAS, W.M. STACEY, Georgia Institute of Technology, M. MURAKAMI, M.R. WADE, Oak Ridge National Laboratory, G.L. JACKSON, General Atomics Predictive simulations of recent radiating mantle DIII D discharges with non-intrinsic seeded impurities such as Ne, Ar and Kr, have been carried out. These L mode and ELMing H-mode discharges often exhibit confinement improvement following the impurity injection. The simulations are performed with the 1-1/2D transport code GTWHIST, which has the capability to calculate the transport of all the charge states of several impurity species along with the main plasma particle and energy transport. The importance of neoclassical effects on the impurity transport, as well as the effect of the enhanced edge radiation on the edge pedestal pressure, the edge pressure gradient, and bootstrap current are also discussed. 1 Supported by U.S. DOE Grant DE-FG02-99ER54538 and Contracts DE-AC05-96OR-22464 and DE-AC03-99ER54463. X Prefer Oral Session Prefer Poster Session John Mandrekas John.mandrekas@me.gatech.edu Georgia Institute of Technology Special instructions: DIII-D Poster Session 1, immediately following NH Brooks Date printed: July 20, 1999 Electronic form version 1.4

OUTLINE AND SUMMARY Experiments with non-intrinsic, seeded impurities are important for the Advanced Tokamak mission of DIII-D. The enhanced edge (mantle) radiation due to the injected impurities lowers the exhaust power from the plasma core, affects edge stability due to the reduction of the edge pressure gradient, and can lead to enhanced confinement due to stabilization of microinstabilities. In this work, results from coupled main plasma and impurity charge state transport simulations are presented for L-mode upper-biased Double- Null discharges with Neon (shot 098775) and Argon (shot 098787) injection, as well as the accompanying reference discharge without impurity injection (shot 098777). Good agreement between simulation and experimental results is obtained using simple transport models for the main plasma and the impurity charge states.

The GTWHIST 1½-D Transport Code Standard time-dependent plasma transport code, solving the flux-surface averaged particle and energy balance equations in the plasma core. 2D fixed-boundary MHD equilibrium solver (VMEC) Models for the calculation of gas puffing fueling, neutral beam heating and current drive, pellet fueling, and other sources and sinks. Self consistent calculation of the transport of all charge states of several impurities (C, O, Ne, Ar, Fe, Kr) Choice of various empirical and theorybased transport models

EQUATIONS in GTWHIST Particle Transport Energy Transport n p j ( Vn j) = ( V Γ j) + VS j V t ρ τ 3 5 2 3 3 5 ( V ) nt e e = ( V ) VQ e+ V TeΓ e + 2 t ρ 2 5 ( ) 3 e Z Z V QE nenqlq ( Te) Qei Q e Z q 3 2 t j E F 5? V 3 n T Z j j 2 5 E F 3? 5 E F 3 i J V V Q j H V Tid j H V? QE HQei JQ j j ê 2 Č Multi-charge state impurity transport d i d i d i Z 1 1 H Z J1 J1J H H H1 H1J H V t Vn n Z V Z I Z n Z q I Z q q R Z Z Z Z q d ~ q q q nq Rq nq S V Z ê í q Z q ~ Γ q Z = D ρ Z q 2 Z nq Z Z + nv q q ρ ρ

TRANSPORT MODELS Main Plasma A simple L-mode Bohm-like transport model 1 has been used for the main plasma particle and energy transport: ( nt e e) 2 χ B = en B e T aq χ = α χ, χ = α χ, D = α χ e e B i i B n B An optional pinch term can be added to the particle transport: Impurities: Č D ~ vp ZJ CV a V 2 ê A fixed-shape transport model has been used for the impurities. All charge states are assumed to have the same diffusion coefficient: D Z D 1Hc ê Z E Z0 1 V ZJ C D a E F c 2 F ~ vz 2 ê Z VZ Z The transport coefficients of the impurity charge states are independent of the main plasma transport coefficients. 1 M. Erba, et al., Plasma Phys. Control. Fusion 37 (1995) 1249.

MODELLING OF REFERENCE DISCHARGE 98777 We first model the reference (no injected impurities) discharge 98777. The simulation starts at about 0.5 s when the plasma has reached its steady-state shape (a, R, κ, δ). Best agreement with experiment is obtained if we use α e = 4.0 10-4, α i = 4.64 10-4 and α n = 3.3 10-4 in the transport model. No pinch term is assumed in the particle transport. The shape of the density profile is determined by the gas-puffing source at the edge and by the fueling source due to 4.5 MW of NB injection. An intrinsic carbon concentration of 1.24% was assumed, raising the peak value of the Z eff to about 1.4, consistent with TRANSP analysis results 2. 2 M. Murakami, et al. Transport Studies of Radiating Mantle Discharges with Confinement Improvement in DIII-D, presented at the RI-Mode Workshop, Culham, 1999.

Comparison of and Experiment for Shot 098777 at t = 1600 ms. 4.5x10 19 Thomson (tangential) 4.0x10 19 Thomson (core) 3.5x10 19 Electron Density (m -3 ) 3.0x10 19 2.5x10 19 2.0x10 19 1.5x10 19 1.0x10 19 5.0x10 18 0.0 Electron Temperature (kev) 3.0 2.5 2.0 1.5 1.0 0.5 0.0 Core Thomson Tang Thomson HECE 3rd

3.5 3.0 Experiment Ion Temperature (kev) 2.5 2.0 1.5 1.0 0.5 0.0 Ion Thermal Diffusivity, χ i (m 2 /s) 10 8 6 4 2 0 TRANSP Analysis ( e e) 2 nt χe= α e aq nb e T 0.0 0.2 0.4 0.6 0.8 1.0

Modeling of Neon Seeded Discharge 98775 In this discharge, Neon was injected at 0.8 seconds, followed by substantial confinement improvement, which was correlated with strong reduction of turbulence 3. No theory-based transport model explaining this confinement improvement and appropriate for use in predictive transport simulations is yet available. In our simulations, the observed confinement improvement is taken into account by reducing the transport coefficient multipliers α e, α i and α n following Neon injection. Best agreement with the experimental profiles was obtained by reducing α e by a factor of 2, α i by a factor of 7 and keeping α n the same. In addition, an inward pinch term (C V = 1, α v = 1) was necessary to match the observed peaking of the density profile. The overall transport reduction is consistent with results obtained from a TRANSP analysis of the experimental data 3. 3 McKee, G. et al., Impurity-Induced Suppression of Turbulence and Transport in DIII- D, presented to the Transport Task Force, Portland, OR, 1999, submitted to Phys. Rev. Lett.; M. Murakami, et al. Transport Studies of Radiating Mantle Discharges with Confinement Improvement in DIII-D, presented at the RI-Mode Workshop, Culham, 1999.

Comparison of and Experiment for Shot 098775 at t = 1600 ms. 6x10 19 Core Thomson Tang. Thomson 5x10 19 Electron Density (m -3 ) 4x10 19 3x10 19 2x10 19 1x10 19 0 Electron Temperature (kev) 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 Core Thomson HECE 3rd Tang Thomson

6 98775.1600 Experiment 5 Ion Temperature (kev) 4 3 2 1 0 98775.1600 4.5 4.0 Experiment 3.5 3.0 Z eff 2.5 2.0 1.5 1.0 0.0 0.2 0.4 0.6 0.8 1.0 Notice that the experimental Z eff contains only the contributions from the fully ionized states of Carbon and Neon (C +16 and Ne +10 ).

Comparison of calculated C and Ne charge states with CER data. 98775.01600 2.8x10 17 C +6 2.4x10 17 Carbon Density (m -3 ) 2.0x10 17 1.6x10 17 1.2x10 17 8.0x10 16 4.0x10 16 0.0 C +5 C +4 18 1.6x10 98775.1600 1.4x10 18 Ne +10 1.2x10 18 Neon Density (m -3 ) 1.0x10 18 8.0x10 17 6.0x10 17 4.0x10 17 2.0x10 17 0.0 Ne +9 Ne +8

Comparison of simulated radiation power profile with fit to data from the bolometer arrays 0.16 Radiated Power (MW/m 3 ) 0.14 0.12 0.10 0.08 0.06 0.04 0.02 0.00 Experiment

Modeling of Argon Seeded Discharge 098787 Similar to Shot 098775, but Argon is injected instead of Neon. Confinement improves following Ar injection, but not as much as in the Ne case. Good agreement with experimental plasma profiles is obtained by reducing the a i coefficient of the Bohm transport term by 2.3 (compared to 7 in the Neon case) following the Ar injection. The same impurity transport model used in the Neon simulations is used for Argon. Good agreement between simulation and experiment for the Ar +16 density profile. Good agreement between simulation and experiment for the C +6 density profile in the edge and central regions. The computed P rad profile agrees well with the profile obtained from a bolometric inversion of the experimental data, although the simulated profile peaks at a smaller radius.

Comparison of and Experiment for Shot 098787 at t = 1600 ms. Electron Density (m -3 ) 5.5x10 19 98787.01600 5.0x10 19 4.5x10 19 4.0x10 19 3.5x10 19 3.0x10 19 2.5x10 19 2.0x10 19 1.5x10 19 1.0x10 19 5.0x10 18 0.0 Experiment Electron Temperature (kev) 3.0 2.5 2.0 1.5 1.0 0.5 0.0 98787.01600 Experiment

5 98787.01600 Ion Temperature (kev) 4 3 2 1 Experiment 0 0.0 0.2 0.4 0.6 0.8 1.0 3.5 98787.01600 3.0 2.5 Z eff 2.0 1.5 1.0 0.0 0.2 0.4 0.6 0.8 1.0

3.0x10 17 98787.01600 2.5x10 17 Ar +16 (CER) Argon Densities (m -3 ) 2.0x10 17 1.5x10 17 1.0x10 17 5.0x10 16 Ar +18 Ar +17 Ar +16 Ar +15 0.0 0.0 0.2 0.4 0.6 0.8 1.0 8.0x10 17 98787.01600 6.0x10 17 C +6 (CER) Carbon Densities (m -3 ) 4.0x10 17 2.0x10 17 C +6 C +5 C +4 0.0

Comparison of simulated radiation power profile with fit to data from the bolometer arrays 0.25 98787.01600 Experiment 0.20 P rad (MW/m 3 ) 0.15 0.10 0.05 0.00

CONCLUSIONS & FUTURE PLANS Results from coupled plasma and multi-charge state impurity transport simulations of L-mode Neon and Argon injected DIII-D discharges and the accompanying reference discharge show good agreement with the experimental data. A simple L-mode Bohm-like model for the main plasma transport and a fixed-shape model for the transport of the impurity charge states appear to be adequate in reproducing the most important features of these discharges. The observed confinement improvement is modeled by a simple reduction of the transport coefficient multipliers of the main plasma following the impurity injection. It was also found that an inward particle pinch was necessary in order to explain the observed electron density profile peaking, following impurity injection. Future plans include the extension of these simulations to other impurity injected DIII-D shots, the implementation and use of a neoclassical model for the transport of the impurity charge states, and the evaluation and eventual use of theory-based models for the energy transport of the main plasma.