Modeling Neutral Hydrogen in the HSX Stellarator

Slides:



Advertisements
Similar presentations
DPP 2006 Reduction of Particle and Heat Transport in HSX with Quasisymmetry J.M. Canik, D.T.Anderson, F.S.B. Anderson, K.M. Likin, J.N. Talmadge, K. Zhai.
Advertisements

Eirene code calculations for the CX spectra of TJ-II (or ‘Close Encounters of the Third Kind with Eirene’) J. Guasp, A. Salas, etc… Index 1. Introduction.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
Magnetic Reconnection Rate and Energy Release Rate Jeongwoo Lee 2008 April 1 NJIT/CSTR Seminar Day.
49th Annual Meeting of the Division of Plasma Physics, November , 2007, Orlando, Florida Ion Temperature Measurements and Impurity Radiation in.
Introduction to Plasma- Surface Interactions G M McCracken Hefei, October 2007.
Edge Neutral Density (ENDD) Diagnostic Overview Patrick Ross Monday Physics Meeting Monday, March19, 2007.
Model prediction of impurity retention in ergodic layer and comparison with edge carbon emission in LHD (Impurity retention in the ergodic layer of LHD)
Profile Measurement of HSX Plasma Using Thomson Scattering K. Zhai, F.S.B. Anderson, J. Canik, K. Likin, K. J. Willis, D.T. Anderson, HSX Plasma Laboratory,
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
30 th EPS conference, St. Petersburg, Russia, July, 7-11, 2003 K.M.Likin On behalf of HSX Team University of Wisconsin-Madison, USA Comparison of Electron.
1 Development of integrated SOL/Divertor code and simulation study in JT-60U/JT-60SA tokamaks H. Kawashima, K. Shimizu, T. Takizuka Japan Atomic Energy.
The toroidal current is consistent with numerical estimates of bootstrap current The measured magnetic diagnostic signals match predictions of V3FIT Comparisons.
V. A. Soukhanovskii 1 Acknowledgement s: R. Maingi 2, D. A. Gates 3, J. Menard 3, R. Raman 4, R. E. Bell 3, C. E. Bush 2, R. Kaita 3, H. W. Kugel 3, B.
Transport of deuterium - tritium neutrals in ITER divertor M. Z. Tokar and V.Kotov Plasma and neutral gas in ITER divertor will be mixed of deuterium and.
14 Oct. 2009, S. Masuzaki 1/18 Edge Heat Transport in the Helical Divertor Configuration in LHD S. Masuzaki, M. Kobayashi, T. Murase, T. Morisaki, N. Ohyabu,
49th Annual Meeting of the Division of Plasma Physics, November 12 – November 16, 2007, Orlando, Florida Ion Species: Cs-133 Initial Energy: 10 keV Launch.
Edge-SOL Plasma Transport Simulation for the KSTAR
Edge characterization experiments in the National Spherical Torus Experiment V. A. Soukhanovskii and NSTX Research Team Session CO1 - NSTX ORAL session,
Radial Electric Field Formation by Charge Exchange Reaction at Boundary of Fusion Device* K.C. Lee U.C. Davis *submitted to Physics of Plasmas.
Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor J.N. Brooks, J.P. Allain Purdue University PFC Meeting MIT,
FEC 2006 Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1, D.L. Brower.
18th International Spherical Torus Workshop, Princeton, November 2015 Magnetic Configurations  Three comparative configurations:  Standard Divertor (+QF)
V. A. Soukhanovskii Lawrence Livermore National Laboratory H. W. Kugel, R. Kaita, A. L. Roquemore Princeton Plasma Physics Laboratory NSTX Research Team.
47th Annual Meeting of the Division of Plasma Physics, October 24-28, 2005, Denver, Colorado ECE spectrum of HSX plasma at 0.5 T K.M.Likin, H.J.Lu, D.T.Anderson,
52nd Annual Meeting of the Division of Plasma Physics, November , 2010, Chicago, Illinois Non-symmetric components were intentionally added to the.
52nd Annual Meeting of the Division of Plasma Physics, November , 2010, Chicago, Illinois 5-pin Langmuir probe configured to measure floating potential.
53rd Annual Meeting of the Division of Plasma Physics, November , 2010, Salt Lake City, Utah 5-pin Langmuir probe configured to measure the Reynolds.
53rd Annual Meeting of the Division of Plasma Physics, November , 2011, Salt Lake City, Utah When the total flow will move approximately along the.
53rd Annual Meeting of the Division of Plasma Physics, November 13 – November 18, 2011, Salt Lake City, UT Laser Blow-Off Impurity Injection Experiments.
= Boozer g= 2*1e -7 *48*14*5361 =.7205 =0 in net current free stellarator, but not a tokamak. QHS Mirror Predicted Separatrix Position Measurements and.
52nd Annual Meeting of the Division of Plasma Physics, November 8 – November 12, 2010, Chicago, IL Development of Laser Blow-Off Impurity Injection Experiments.
Plasma Turbulence in the HSX Stellarator Experiment and Probes C. Lechte, W. Guttenfelder, K. Likin, J.N. Talmadge, D.T. Anderson HSX Plasma Laboratory,
56th Annual Meeting of the Division of Plasma Physics, October 27 – October 31, 2014, New Orleans, LA Increase ion temperature with neutral beams: Study.
54th Annual Meeting of the APS Division of Plasma Physics, October 29 – November 2, 2012, Providence, Rhode Island 3-D Plasma Equilibrium Reconstruction.
18 th Int’l Stellarator/Heliotron Workshop, 29 Jan. – 3 Feb. 2012, Canberra – Murramarang Reserve, Australia Recent Results and New Directions of the HSX.
57 th Annual Meeting of the Division of Plasma Physics. November 16-20, Savannah, GA 1.Stangeby, P. C. The plasma boundary of magnetic fusion devices.
56 th Annual Meeting of the Division of Plasma Physics. October 27-31, New Orleans, LA Using the single reservoir model [3], shown on right, to:
54 th APS-DPP Annual Meeting, October 29 - November 2, 2012, Providence, RI Study of ICRH and Ion Confinement in the HSX Stellarator K. M. Likin, S. Murakami.
57th Annual Meeting of the Division of Plasma Physics, November , Savannah, Georgia Equilibrium Reconstruction Theory and Modeling Optimized.
Profiles of density fluctuations in frequency range of (20-110)kHz Core density fluctuations Parallel flow measured by CHERS Core Density Fluctuations.
54th Annual Meeting of the Division of Plasma Physics, October 29 – November 2, 2012, Providence, Rhode Island 5-pin Langmuir probe measures floating potential.
48th Annual Meeting of the Division of Plasma Physics, October 30 – November 3, 2006, Philadelphia, Pennsylvania HIBP Designs for Measurement of the Electric.
Measurements of Reynolds stress flow drive and radial electric fields in the edge of HSX Bob Wilcox HSX Plasma Laboratory University of Wisconsin, Madison.
Neoclassical Predictions of ‘Electron Root’ Plasmas at HSX
Numerical investigation of H-mode threshold power by using LH transition models 8th Meeting of the ITPA Confinement Database & Modeling Topical Group.
0.5 T and 1.0 T ECH Plasmas in HSX
Development of CR Model for OES in Hydrogen Plasma
Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik1, D.L. Brower2, C. Deng2,
Features of Divertor Plasmas in W7-AS
Similarities and differences in SOL physics
Magnetic fluctuation measurements in HSX and its impact on transport
Impurity Transport Research at the HSX Stellarator
Recycling and impurity retention in high-density,
Generation of Toroidal Rotation by Gas Puffing
Finite difference code for 3D edge modelling
S. P. Gerhardt, A. Abdou, A. F. Almagri, D. T. Anderson, F. S. B
Characteristics of Biased Electrode Discharges in HSX
Targeted Physics Optimization in HSX
Characteristics of Edge Turbulence in HSX
Overview of Recent Results from HSX
Studies of Bias Induced Plasma Flows in HSX
2/13 Introduction Knowledge of the influence of the hydrogen isotope on H-mode confinement is essential for accurately projecting the energy confinement.
First Experiments Testing the Working Hypothesis in HSX:
Targeted Physics Optimization in HSX
Development and Analysis of Gas Puff CXRS in SOL
Comparisons of Measurements and Gyro-kinetic Simulations of Turbulence and Trans-port in Alcator C-Mod EDA H-Mode Discharges M. B. Sampsell, R. V. Bravenec.
Evaluation of the main ion flow and temperature using the GPI system
XGC simulation of CMOD edge plasmas
Summary Slide Title: Effect of multiple periodic gas puff on neutral temperature in aditya – u tokamak Measurement of neutral temperature in the edge region.
Presentation transcript:

Modeling Neutral Hydrogen in the HSX Stellarator L. Stephey, A. Bader, D.T. Anderson, J.N. Talmadge, C. Hegna, F.S.B. Anderson HSX Plasma Laboratory, Univ. of Wisconsin, Madison, USA Overview Simulation of Supersonic Gas Injector (SGI) The HSX neutral particle population plays an important role in plasma behavior as a result of relatively low operating density The DEGAS code [1] is a fully 3D Monte-Carlo neutral particle code that is used to simulate the HSX neutral population H-alpha measurements are used to scale DEGAS results to determine quantities including atomic and molecular neutral particle density, neutral particle flux, and ionization rate The DEGAS code has been recently upgraded to simulate a supersonic gas injector (SGI) in HSX Simulation results indicate: SGI performance will vary by location as a result of distance between SGI and core plasma An SGI in the same location as the current gas puff will increase fueling efficiency from 43 to 47 percent Because DEGAS simulations are steady-state, most likely the predicted fueling efficiency is somewhat overestimated The DEGAS code has been compared to the EMC3-EIRENE code [2] Both predict the same general picture of neutral behavior DEGAS predicts a steeper falloff of H and H2 density in the edge EMC3-EIRENE predicts a region of low H2 density outside the separatrix Several types of wall fueling scenarios were simulated in an attempt to better match H-alpha array data Simulations were able to match measurements relatively well when puffing from C-puffer Simulations were unable to match measurements when puffing from A’-puffer Results suggest that we are not accurately modeling particle fueling and recycling from the HSX wall A n H-alpha camera diagnostic may be used to study HSX wall recycling and developed an improved model Supersonic gas injection is a method of fueling that has been used by many experiments to increase fueling efficiency [3,4] A laval nozzle (pictured in Fig. 1) is used to create a narrow cone of supersonic particles DEGAS has been upgraded to simulate the installation of an SGI on HSX Gas puff energy was increased from 0.026 eV to 0.06 eV Particle launch angle was changed from a cosine distribution to a narrow zcone with a 4.5 degree half-angle The puff and SGI were simulated in the same location with the same particle source rate and background plasma Simulations indicate that an SGI can increase fueling efficiency compared to the current gas puff system, but also that it is highly dependent upon position This is most likely due to the differences in distance between the SGI locations and the center plasma DEGAS directly calculates the H and H2 ionization rate at each point in the computational grid The particle source rate is directly input by the user The H ionization rate within the separatrix and the particle source rate are used to calculate the fueling efficiency [5] The SGI was simulated in six poloidal positions at the same toroidal angle Overall H profiles were relatively unchanged, but SGI fueling generally decreased the H2 profile in the edge region as compared to the gas puff Fueling efficiency was highly dependent on position– most likely due to differences in distance to the center of the plasma Fig.2. Background plasma in DEGAS simulations. Based on experimental Thomson profiles. Fueling efficiency is calculated by where is the H ionization rate in the volume and is the particle source rate SGI grid position Fueling efficiency 9 52.34 18 40.30 27 47.43 36 50.15 45 54 47.15 H ionization rate Particle source rate Fueling efficiency Puff 2.6e23 6e23 43.44 SGI 2.8e23 47.15 Because DEGAS predicts steady state quantities, it is likely that the fueling efficiency is somewhat overestimated as transient behavior is ignored Fig.5. Plots of H neutral density and H ionization rate for various SGI positions (colors) and gas puff (black). Fig.6. Plots of H2 neutral density and H2 ionization rate for various SGI positions (colors) and gas puff (black). Fig. 1. A typical laval nozzle. HSX will install an SGI system with this type of nozzle with a 4.5 degree half-angle launch cone. Fig.7. SGI was simulated in these six poloidal positions. Total neutral density is shown for each SGI simulation. Corresponding fueling efficiencies are tabulated in the table to the right. Fig.3. Log plots of total neutral density for puff (top) and SGI (bottom). Fig.4. Log plots of H ionization rate for puff (top) and SGI (bottom). Comparison to EMC3-EIRENE Efforts to Match H-alpha Measurements Summary and Future Work A’ puffer DEGAS EMC3-EIRENE H2 H log H log H2 C puffer HSX is currently equipped with 16 H-alpha detectors (and the system will soon be expanded by 20 detectors) 9 of these detectors are in a poloidal array in field period C and the rest are in a toroidal array extending around HSX DEGAS synthetic H-alpha light is scaled by measured H-alpha in order to obtain calculated neutral quantities Several wall fueling configurations were simulated The current HSX strike point model [6] The whole wall as a source Half the wall (every other point) as a source DEGAS simulations match reasonably well with poloidal measurements when using C gas puff (very close to poloidal array) DEGAS simulations do not replicate all features of toroidal measurements for the C gas puff No wall fueling configuration was able to match poloidal or toroidal H-alpha measurements in poloidal array when using A’ puffer This suggests that we are not correctly modeling fueling from the wall Possible future work: develop a better model of wall fueling in HSX DEGAS simulations indicate that far from the gas puff, most H-alpha light is produced near the wall (Fig.10) This could be studied with an H-alpha filtered camera Installing an SGI on HSX is predicted to improve fueling efficiency from 43 to up to 52 percent SGI performance will vary from 40 to 52 depending on location DEGAS has been compared to EMC3-EIRENE for HSX and both generally agree Several wall configurations were simulated to in an attempt to match DEGAS predictions to H-alpha data Simulations matched C puff data relatively well Simulations did not match A’ puff data This suggests the current HSX wall fueling model is incorrect Future work: Complete installation of 2 new H-alpha arrays (20 detectors) on HSX Install SGI on HSX and compare to simulation Consider upgrading to DEGAS 2 [7] if further simulations are needed (faster, newer and currently maintained) Use an H-alpha filtered camera system to study plasma wall recycling far from gas source Use information from H-alpha camera to develop more accurate model of plasma recycling in HSX and investigate role of neutrals in the SOL DEGAS and EMC3-EIRENE simulations for HSX neutral particles were compared Efforts were made to make as direct a comparison as possible: Similar values of Te, Ti, ne, and ni throughout the plasma grid The same (HSX) geometry and magnetic configuration (QHS) Same (single) toroidal angle Same wall material (carbon) Results: Both agree on the same general picture DEGAS predicts a steeper falloff in neutral density near the edge EMC3-EIRENE predicts a region of low H2 just outside the separatrix There are several factors that may contribute to these differences: DEGAS Te, Ti, ne, and ni profiles are directly input whereas EMC3-EIRENE calculates these profiles DEGAS particle source rate from the wall is directly input whereas it is calculated by EMC3-EIRENE EMC3-EIRENE includes islands, flows, and subsequent poloidal variation in plasma density, temperature, and flow profiles that DEGAS does not Future work may include Comparisons at more than one toroidal angle Comparisons of puff fueling behavior Strike points Whole wall Half wall A’ puffer Strike points Fig.8. Plots of H, H2, log H, and log H2 density as predicted by DEGAS and EMC3-EIRENE at this particular toroidal angle (45 degrees). The center of the DEGAS log H2 plot has been omitted to remove noise near the plasma center. EMC3-EIRENE plots courtesy of A. Bader. References Fig.9. Flux surface averaged H and H2 as predicted by DEGAS and EMC3-EIRENE. Densities have been normalized to be equal at r/a=1. Flux surface averaged results can only be compared in this region as a result of the EMC3-EIRENE computational grid. EMC3-EIRENE results courtesy of A. Bader. Whole wall Fig.10. DEGAS predicted total H-alpha emission at two toroidal angles far from the gas puff source. Results suggest that most emission is produced close to the wall and could be investigated with a camera diagnostic. [1] D. Heifetz et al., J. Comp. Phys. Vol. 46, Pg. 309 (1982). [2] Y. Feng et al, Contribution Plasma Physics, 44 1-3 (2004) p. 57-69. [3] V. Soukhanovskii et al., Rev Sci. Instruments. Vol. 75, No. 10 (2004). [4] T. Mizuuchi et al., Contrib. Plasma Phys. 50, No 6-7 (2010). [5] D. Lundberg. Dissertation. PPPL. (2012). [6] J. M. Canik et al., Phys. Plasmas Vol. 14, Pg. 056107 (2007). [7] D. P. Stotler et al., J. Nucl. Mater. Vol. 967, Pgs. 290–293 (2001). Fig.11. A schematic of HSX that indicates the location of the two gas puffs, the H-alpha poloidal array, and the H-alpha toroidal array. Half wall