Investigation of causes for the discrepancy between the measured and modeled helium emissions using a gas puff imaging diagnostic

Similar documents
Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod

Connections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod

Blob sizes and velocities in the Alcator C-Mod scrapeoff

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

Plasma Science and Fusion Center

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation

Development of a New Gas Puff Imaging Diagnostic on the HL-2A Tokamak

ICRF Loading Studies on Alcator C-Mod

Sensitivity of Tokamak Transport Modeling to Atomic Physics Data: Some Examples

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes

Modeling neutral-plasma interactions in scrape-off layer (SOLT) simulations*

Invited Review Article: Gas Puff Imaging Diagnostics of Edge Plasma Turbulence in Magnetic Fusion Devices. X Science LLC, Plainsboro, NJ 08536, USA

Measurement of lower hybrid waves using microwave scattering technique in Alcator C-Mod

Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer

A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments

Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer

High Speed Imaging of Edge Turbulence in NSTX

Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod

Predicting the Rotation Profile in ITER

Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod

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

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

Physics of the detached radiative divertor regime in DIII-D

Alcator C-Mod. Particle Transport in the Alcator C-Mod Scrape-off Layer

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

Non-local Heat Transport in Alcator C-Mod Ohmic L-mode Plasmas

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices

DNB Program. W.L. Rowan, D. Beals, R.V. Bravenec, M.B. Sampsell, D.M. Patterson Fusion Research Center, University of Texas at Austin

A Motional Stark Effect Instrument to Measure q(r) on C-Mod

Edge Zonal Flows and Blob Propagation in Alcator C-Mod P5.073 EPS 2011

Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod

Experimental investigation of the parallel structure of fluctuations in the scrape-off layer of Alcator C-Mod

Propagation of Radio Frequency Waves Through Fluctuations in Plasmas

Impact of neutral atoms on plasma turbulence in the tokamak edge region

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

This is a repository copy of Radial localization of edge modes in Alcator C-Mod pedestals using optical diagnostics.

Active Spectroscopy. Neutral Beam Diagnostics for Alcator C-Mod

Plasma impurity composition in Alcator C-Mod tokamak.

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod

Operational Phase Space of the Edge Plasma in Alcator C-Mod

Dimensionless pedestal identity plasmas on Alcator C-Mod C

Effect of secondary beam neutrals on MSE: theory

Plasma Radiation. Ø Free electrons Blackbody emission Bremsstrahlung

Neutral Beam-Ion Prompt Loss Induced by Alfvén Eigenmodes in DIII-D

Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod

Gyrokine.c Analysis of the Linear Ohmic Confinement Regime in Alcator C- Mod *

This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract

Observations of Rotation Reversal and Fluctuation Hysteresis in Alcator C-Mod Plasmas

Rapid changes of turbulence propagation direction in the edge of

Implementation of a long leg X-point target divertor in the ARC fusion pilot plant

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

Helium ELMy H-modes in Alcator C-Mod in Support of ITER Helium Operating Phases

Critical edge gradients and flows with reversed magnetic field in Alcator C-Mod

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices!

Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas

A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor

Simulation of Plasma Flow in the DIII-D Tokamak

Modelling of JT-60U Detached Divertor Plasma using SONIC code

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

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D

Experimental Results on Pellet Injection and MHD from the RTP Tokamak

LCDC IN TOKAMAKS. THE LOCAL COLD AND DENSE COMPRESS What to Measure and How to Measure. Waseda University 2

Progress of Confinement Physics Study in Compact Helical System

CONFINEMENT OF INJECTED SILICON IN THE ALCATOR A TOKAMAK

Improved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas

Improved absolute calibration of core Thomson scattering(ts) diagnostics on Alctor C-Mod

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

D. Smith, R. Fonck, G. McKee, D. Thompson, and I. Uzun-Kaymak

L-to-H power threshold comparisons between NBI and RF heated plasmas in NSTX

ICRF Induced Argon Pumpout in H-D Plasmas in Alcator C-Mod

ICRF Minority-Heated Fast-Ion Distributions on the Alcator C-Mod: Experiment and Simulation

The Neutron Diagnostic Experiment for Alcator C-Mod

A neoclassical model for toroidal rotation and the radial electric field in the edge pedestal. W. M. Stacey

Investigation of Water Fragments

The Instrumental Function of the X-ray Imaging Crystal Spectrometer on Alcator C-Mod

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

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

Lower Hybrid RF: Results, Goals and Plans. J.R. Wilson Alcator C-Mod Program Advisory Meeting January 27, 2010

PFC/JA MEASUREMENT OF THE D-D FUSION NEUTRON ENERGY SPECTRUM AND VARIATION OF THE PEAK WIDTH WITH PLASMA ION TEMPERATURE

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

ITB Transport Studies in Alcator C-Mod. Catherine Fiore MIT Plasma Science and Fusion Center Transport Task Force March 26th Boulder, Co

Cross-Field Transport in the SOL: Its Relationship to Main Chamber and Divertor Neutral Control in Alcator C-Mod

Divertor physics research on Alcator C-Mod. B. Lipschultz, B. LaBombard, J.L. Terry, C. Boswell, I.H. Hutchinson

Cross-field plasma transport and main chamber recycling in diverted plasmas on Alcator C-Mod. Abstract

The Levitated Dipole Experiment: Towards Fusion Without Tritium

Fluctuation statistics in the scrape-off layer of Alcator C-Mod

Cesium Dynamics and H - Density in the Extended Boundary Layer of Negative Hydrogen Ion Sources for Fusion

Development of the Gas Puff Charge Exchange Recombination Spectroscopy (GP-CXRS) Technique for Ion Measurements in the Plasma Edge

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

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

Application of Magnetically-Broadened Hydrogenic Line Profiles to Computational Modeling of a Plasma Experiment

Neutral Density Profiles From a Diverted Plasma in Alcator C-Mod. Christopher Paul Barrington-Leigh

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

The New Sorgentina Fusion Source Project

Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields

Comments on Particle and Energy Balance in the Edge Plasma of Alcator C-Mod

ArbiTER studies of filamentary structures in the SOL of spherical tokamaks

Transcription:

Investigation of causes for the discrepancy between the measured and modeled helium emissions using a gas puff imaging diagnostic S. Baek, J. Terry, D. P. Stotler*, D. Brunner, B. LaBombard MIT Plasma Science and Fusion Center *Princeton Plasma Physics Laboratory 59th Annual Meeting of the Division of Plasma Physics Milwaukee, Wisconsin October 23, 2017 1/11

Goal: Validate a neutral transport code for a quantitative study of neutral transport using a gas-puff imaging (GPI) diagnostic GPI measurements are useful in studying plasma fluctuations at the tokamak boundary. Theodorsen CO4.00012, Kube YI2.00003 The absolute brightness profile comparison with DEGAS 2* is useful for: Code validation (first time with helium) GPI design We compare the profiles in the D2- and he- puff experiments, and attribute the discrepancy observed in the he-puff case to: Gas puff perturbations Plasma fluctuations 2-D Helium I line brightness (587 nm) profile Z LCFS R *Stotler, http://w3.pppl.gov/degas2/ 2/11

3/11 A gas puff imaging diagnostic on Alcator C-Mod Side View of C-Mod Tokamak A nozzle that puffs deuterium molecules or helium atoms at the low-field-side. A optics system that images the emission with a rectangular field of view (4 cm x 4 cm). Both the gas puff flow rate and detector response are absolutely calibrated.

4/11 A good agreement is found between the experimental and modeled D α brightness profiles. (n e /n G = 0.2) Both the peak brightness and the profile shape are well-matched. In line with the previous study on NSTX [Cao, FST (2009)].

The experimental helium peak brightness is lower by a factor of three than the modeled peak brightness. (n e /n G = 0.2) (n e /n G = 0.7) The profile shape is not reproduced at higher densities. The shifts in the input n e & T e profiles did not resolve the discrepancy. A better match is found with the decrease in the input T e. 5/11

The injected helium neutrals remain cold. Deuterium atoms have a relatively high energy. Dissociation ( ~ 3 ev) from the injected D 2 molecules Charge exchange Helium atoms Weak elastic scattering with D + Remain cold (~0.026 ev) with a short mean free path Incoming Neutral Flux Helium neutrals have a weaker penetration, and they are less dispersive in space than deuterium neutrals [Stotler JNM (2007), Cao FST (2009)] Labombard, KN1D, PSFC/RR-01-3 (2001) 6/11

7/11 Electron cooling can occur via neutral ionizations. Gas-puff cooling might cause a drop in T e on the flux tubes that intersect the gas cloud. DEGAS 2 Result The SOL ne & Te profile measurement location is not on the same flux tube. Cooling rate (kw/m 2 ) along the toroidal direction can be estimated from DEGAS 2. (n e /n G = 0.7)

8/11 The cooling effect can be significant in the far SOL. The cooling rate (q,loss ) can be compared with the heat flux required to sustain the measured T e. (n e /n G = 0.7) q 200 kw/m 2 for T u = 10 ev q k 0 T u 7 2 /(3.5 L) where k 0 = 2000 [W/m/eV 7/2 ] & L 10 m for C-Mod q,loss > q for Te 10 ev Consistent with the model analysis (i.e., the need for the drop in T e )

9/11 Another possible cause is the presence of plasma fluctuations. Time series of the measured n e & T e T e n e S ion ( n e, T e ) is used in the model But, S ion ( n e, T e ) S ion (n e, T e ) Modeling studies [Marandet AIP 2017] show: Increase in the effective ionization rate in the presence of the T e fluctuation. Neutrals with a short m.f.p. are more susceptible to the time-dependent effect. Effective ionization rate can experimentally be evaluated using the high-resolution SOL data.

Effective ionization rate can be increased up to 50% at high density. The effective emission rate coefficient is 10% lower than that evaluated from <n e > & <T e >. With the effective ionization rate of S ion, eff = 1.5 S ion, the neutral density is found to decrease by ~15% in a simple 1D model. The effective emission decreases by 25% at high density. Helium-puff experiments 10/11

11/11 Summary In the GPI experiment, the measured helium brightness peak is found to be lower by a factor of than the modeled brightness peak. In the low T e region, the gas-puff cooling may be significant, consistent with the model analysis. At a high density, plasma fluctuations can partially be responsible for the discrepancy (~25%). Implications in the helium GPI data anaysis: Gas puff perturbation effects may need to be considered. Helium neutral transport may be subject to plasma fluctuation effects.