Impurity transport analysis & preparation of W injection experiments on KSTAR
|
|
- Gerald McDowell
- 5 years ago
- Views:
Transcription
1 Impurity transport analysis & preparation of W injection experiments on KSTAR J. H. Hong, H. Y. Lee, S. H. Lee, S. Jang, J. Jang, T. Jeon, H. Lee, and W. Choe ( ) S. G. Lee, C. R. Seon, J. Kim, ( ) 마스터부제목스타일편집 I. N. Bogatu ( ) S. Henderson and M. O Mullane ( ) D. Pacella ( )
2 Outline 1. Introduction - Current issues on W in tokamak plasmas 2. Current analysis tools for impurity transport study on KSTAR - ADAS-SANCO impurity code analysis - Diagnostics: SXR and VUV 3. Preparation of W experiments - Development of W injection system - Upgrading diagnostics : SXR and VUV - Estimation of Ar & W emission power on KSTAR for designing SXR filters 4. Summary
3 Impurities in fusion plasmas Origin of Impurities - Plasma-wall interaction: C, Fe, Be, W, - Fusion reaction: He (alpha particle) - Deliberately introduced: Ne, Ar, Si Effects in tokamak - Diluting fuel ions and reducing heating efficiency & plasma reactivity - Enhancing radiation power losses especially in the core by central accumulation - Can be used for diagnostic purpose and shielding of the wall from excessive load Ideal impurity profile - Mantle in the Edge - Low in the Core ne (r) nimp (r) It is important to understand transport of impurities in order to prevent central accumulation and its negative consequences r/a
4 Current issues on W in tokamak plasmas Influence of W divertor on the access to the H-mode Effect of W divertor on pedestal parameters and plasma confinement Predicted impacts of wall and divertor material on pedestal structure High radiation loss from W core accumulation R. Neu, ADAS Workshop, 2007, Ringberg ITPA: Transport of high Z impurities (including W) in the core plasma and possibilities for its control W injection experiments on KSTAR (superconducting machine)
5 Current analysis tools for impurity transport study on KSTAR - Focused on Ar injection experiments Transport codes (ADAS-SANCO) Diagnostics (SXR & VUV)
6 Impurity transport analysis SANCO (collaboration with JET) 1D radial continuity equation - Radial particle flux Diffusion coefficient : impurity ion density : particle flux via magnetic surface : source and sink (ionization & recombination from ADAS) Convection coefficient Experimental data Fitting Impurity transport modelling KSTAR diagnostics - Soft X-ray array - VUV spectrometer - X-ray imaging crystal spectrometer, etc D, V determination - Impurity transport code SANCO - Fitting analysis code UTC
7 Soft X-ray arrays with Ar Ross filter KSTAR D-port X-ray Ross Filter (XRF) NaCl and CaF 2 Band pass filter within the narrow region between their L III or K absorption edges 16 ch (32) HU HD 16 ch (32) kev Ar 13+, Ar 14+, Ar 15+, mainly Ar 16+, Ar 17+
8 Model for Ar emission in soft X-ray range (1) Calculation of local Ar radiation power (r,t) Power coeffs of Line Transition Power coeffs of RecomBination (2) Response function of Ross filter (3) LoS calculation and line integration
9 ITER VUV spectrometer prototype Collaboration with ITER KO-DA (C.R. Seon) Current (15-60 nm, ~13-40 ms) (1) Measurable major line transitions VUV spectrometer on the optical table 1 ch, survey Vacuum extension He I nm He II nm O V : 15.61, 19.28, nm O VI : 17.30, nm C III : nm C IV : 24.49, 38.41, nm C V : 22.72, nm Fe XV : nm Fe XVI : 33.54, nm Ar XIV nm Ar XV nm Ar XVI nm (2) Modeling of Ar line transitions - All atomic coefficients are from ADAS
10 Preparation of W experiments - Development of W injector system - Upgrading current diagnostics (VUV & SXR) - Estimation of W & Ar emission power on KSTAR for designing filters of new SXR system
11 Candidates for the W particle injector Laser blow-off system (C-Mod) - Well controlled temporal form of the source function - Adjustable injecting amount of particles - Difficulties : high cost (laser system), short preparation time Pellet injection (LHD) - Can deposit impurities deep inside the confined plasma - Difficulties : designing of pellet, short preparation time Particle dropper (NSTX) - Simple design, easy to inject W dusts into plasmas - Difficulties : A lack of install locations (need to modify passive stabilizer and upper port of KSTAR) Using H-port halls on PS? It is required to try a simple injector system under the current condition for first W injection experiments on KSTAR.
12 Design of Tungsten Injection System Design goals 1) Flight-distance of particles > 10 cm Injection system will be mounted on the manipulator The manipulator is inserted into the vacuum vessel around 10 cm away from the LCFS. 2) Compact size Gun: diameter ~ 8 mm, length ~ 50 mm Piezo-electric motor (R40NM, Piezo technology ) 10 cm 3) Tolerance for strong B-field & high vacuum environments STS316 Piezo-electric motor (R40NM, Piezo technology ) 4) Reloadable system in preparation 5) Capability to inject a small amount of metal particles
13 Experimental Set-up Target plate position: l =100 mm Central axis (y,z)=(0,0) on the target plate A piezoelectric motor moves the trigger. Pictures of deposited particles on the target plate are taken by a DSLR camera (CANON EOS 500D).
14 Example of Performance Test (y,z)=(0,0): central axis evaluated from edges of injection gun (Injection gun s diameter ~ 8 mm) 0.2 mm diameter of Cu, l = 100 mm Deposited locations Averaged drop Cu particles on the target plate Edges 10 mm To evaluate deposited locations 2-D distribution image z To estimate 2-D distribution y
15 Particle size (W 0.2, 0.1 & 0.06 mm) Target plate: 10 cm away from the injection gun Launched W particles 0.2, 0.1 & 0.06 mm, (10 mg x 5 times = 50 mg) Amount of particles reached to the target plate Less than 2 mg (< 5%) Distribution of l = 10 cm 1) Averaged vertical drop at the target plate mm: Δz = mm mm: Δz = mm mm: Δz = mm 2) Average initial velocity (v 0 ): ignoring air resistance - v 0 ~ 2.3 m/s (like sputtering from wall) z 1 2 gt 2 l v 0 t In the case of W, particle size does not affect change of averaged drop
16 Distribution of W on the target plate I (a) (b) (c) 0.06 Deposited locations of launched W particle on the target plate (a) 0.2 mm, (b) 0.1 mm, and (c) 0.06 mm
17 Distribution of W on the target plate II (a) (b) (c) 0.06 Distribution of launched W particle on the target plate (a) 0.2 mm, (b) 0.1 mm, and (c) 0.06 mm
18 W dust dropper system from NSTX Collaboration with PPPL (NSTX team) Dust selector Compact version Clementson et al. Rev. Sci. Instrum. 81, 10E Vibrator Using KSTAR H-port? (supposed to be used for SXR)
19 VUV imaging spectrometer This summer(5-20 nm, ms) 28 ch, imaging Collaboration with ITER KO-DA (C.R. Seon) Preparation in laboratory Active pixels: 1024 x 256 Pixel size (W x H): 26 x 26 μm Image area: 40 mm x 12mm of MCP adopted to CCD of nm He II from Hollow Cathode Lamp ~5.5 mm Slit Imaged to CCD Slit Pattern Spacing ~ 2mm 5~7 nm quasi-continuum nuum peaks of W are expected 24.6 nm 23.4 nm Clementson et al. Rev. Sci. Instrum. 81, 10E
20 Soft X-ray array system Current This summer 2 arrays, 64ch 4 arrays, 256 ch 1 array, 48 ch VU2 edge 16 ch (32) HU HD 16 ch (32) VD2 HU HD Be filters (10, 50 um) Ar Ross filters ( kev Ar 16+, Ar 17+ ) Bolometer (No filter) 4 arrays, 256 chs 2D Tomography Poloidal asym. study < 2 cm, 2 μs 3 filters multi energy, neural network < 1.3 cm, 2 μs 2D fast MHD & transport study
21 Estimation of W & Ar emission power For designing new multi-array SXR filter to measure W & Ar emission, ADAS-SANCO simulation has been done Input EFIT D, V (Trial value) Background (T e, n e ) Impurity Influx T e, n e n z (r, t) SANCO Calculates - n z (r, t) for every charge states z of W & Ar ADAS Calculates line emission for every line transition Line integration along LOS Final power spectrum of W & Ar
22 Input profiles for ADAS-SANCO (1) T e & n e profiles of typical KSTAR L-mode and H-mode - Evaluated by ECE, TS, interferometer L-mode H-mode L-mode H-mode n e [ m -3 ] T e [kev] r/a (2) Influx : flow meter signal for both W & Ar r/a (3) EFIT Recycling rate Ar = 0.6 W = s By S. Sabbagh
23 Input profiles for ADAS-SANCO - D & V for L mode (experimentally obtained from KSTAR #7574 Ar) Diffusion (m 2 /s) Convection (m/s) r/a - D & V for H mode (from ASDEX-U results) r/a T. Putterich, 2005, Investigations on Spectroscopic Diagnostic of High-Z Elements in Fusion Plasmas, PhD Thesis University Augsburg
24 W & Ar emission spectrum under KSTAR condition L-mode case H-mode case W cm- W/cm 2 ev 3-1 ev W quasi-continuum nuum (VUV) W peaks Ar peaks (Ross filter) W W/cm cm- 2 ev 3 ev W peaks Ar peaks (Ross filter) X-ray energy (kev) X-ray energy (kev) Continuum radiation was calculated by where Z eff ~ 2.5 with C dominant situation S. von Goeler et al., Nucl. Fusion 15, 301 (1975)
25 Expected studies 1. Z-dependence study of impurity transport JET result - Simultaneous injection of Ar & W for the 2014 campaign Closed symbol: [Dmeas, Vmeas] Open symbol: [Dmeas, Vneo] ne /<ne> 0 Giroud C. et al 13 th ITPA Confinement Database & Modelling Topical Group, Naka, Japan H Nordman et al, 2011 Plasma Phys. Control. Fusion - Various turbulent-based transport theories have been trying to estimate impurity transport with varying Z. Nevertheless, there is no theory explaining experimental results well. - It is required to have more experimental data to develop and revise impurity transport models.
26 Expected studies 2. Control impurity transport by applying auxiliary power 4.5 x No ECH Total Ar Ar +16 Ar x On-axis ECH Total Ar Ar +16 Ar #/m #/m r/a Controllability of Ar impurity was confirmed by ECH on KSTAR. - Applying ICRH, ECCD as well. - Effects on not only Ar but also W. 3. Effects of RMP on impurity transport - Find out the relationship and mechanism between magnetic perturbation and impurity transport from edge (ELM) to core (impurity accumulation). - Applying MP after injection and before injection. r/a
27 Expected studies 4. Impurity formation of poloidal asymmetry H-mode ICRH L-mode C-Mod Mo injection C-Mod, Mo injection M Reinke, et al., E1/E2 Task force meeting Full 2-D tomography reconstruction will be available with vertical arrays Finding poloidal asymmetry of high-z impurities such as W Comparing between Ar & W cases - For various plasma modes and conditions
28 Summary Impurity transport analysis tools on KSTAR - ADAS-SANCO impurity transport code - Soft X-ray array system and VUV spectrometer system - It has well worked for KSTAR Ar injection experiments since W injection experiment is under preparation on KSTAR - Injecting system : W injector gun, W dust dropper (Collaboration with NSTX) - Imaging VUV spectrometer having W quasi-continuum peaks is installed on KSTAR F-port. - Additional SXR arrays will be installed on KSTAR D-port with Be filters for W and Ar measurement. - ADAS database set is also ready for simulating W emissions in fusion plasmas.
Application of atomic data to quantitative analysis of tungsten spectra on EAST tokamak
Technical Meeting on Uncertainty Assessment and Benchmark Experiments for Atomic and Molecular Data for Fusion Applications, 19-21 December 2016, Vienna, Austria Application of atomic data to quantitative
More informationModification of argon impurity transport by electron cyclotron heating in KSTAR H-mode plasmas
Modification of argon impurity transport by electron cyclotron heating in KSTAR H-mode plasmas Joohwan Hong 1,2, S. S. Henderson 3, Kimin Kim 1,2, C. R. Seon 4, Inwoo Song 1,2, H. Y. Lee 1,2, Juhyeok Jang
More informationIntroduction to the Diagnosis of Magnetically Confined Thermonuclear Plasma
Introduction to the Diagnosis of Magnetically Confined Thermonuclear Plasma Core diagnostics II: Bolometry and Soft X-rays J. Arturo Alonso Laboratorio Nacional de Fusión EURATOM-CIEMAT E6 P2.10 arturo.alonso@ciemat.es
More informationImpurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U
1 EX/P4-25 Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-6U T. Nakano, H. Kubo, N. Asakura, K. Shimizu and S. Higashijima Japan Atomic Energy Agency, Naka,
More informationEX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier
EX/C-Rb Relationship between particle and heat transport in JT-U plasmas with internal transport barrier H. Takenaga ), S. Higashijima ), N. Oyama ), L. G. Bruskin ), Y. Koide ), S. Ide ), H. Shirai ),
More informationDisruption mitigation in ITER
Disruption mitigation in ITER S.Putvinski, R.Pitts, M.Sugihara, L.Zakharov Page 1 Outline Introduction Massive gas injection for mitigation of thermal loads Forces on VV and in vessel components Suppression
More informationITER A/M/PMI Data Requirements and Management Strategy
ITER A/M/PMI Data Requirements and Management Strategy Steven Lisgo, R. Barnsley, D. Campbell, A. Kukushkin, M. Hosokawa, R. A. Pitts, M. Shimada, J. Snipes, A. Winter ITER Organisation with contributions
More informationBolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy)
Bolometry H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy) Revised May 28, 2002 1. Radiated power Time and space resolved measurements of the total plasma radiation can be done by means
More informationRecent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science
Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant
More informationICRF Induced Argon Pumpout in H-D Plasmas in Alcator C-Mod
ICRF Induced Argon Pumpout in H-D Plasmas in Alcator C-Mod C. Gao, J.E. Rice, M.L. Reinke, Y. Lin, S.J. Wukitch, L. Delgado-Aparicio, E.S. Marmar, and Alcator C-Mod Team MIT-PSFC, University of York, Princeton
More informationTungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER
Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER M.L. Reinke 1, A. Loarte 2, M. Chilenski 3, N. Howard 3, F. Köchl 4, A. Polevoi 2, A. Hubbard 3, J.W. Hughes
More informationTungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER
Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER A. Loarte ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex, France
More informationAbstract. PEGASUS Toroidal Experiment University of Wisconsin-Madison
Abstract Measurement capabilities for the Pegasus ST are increasing to support the scientific studies of plasma behavior at very-low A. Global parameters are obtained from equilibrium reconstructions constrained
More informationSpectroscopic studies of impurities in the LHD plasmas
Spectroscopic studies of impurities in the LHD plasmas Visitor: Zhenwei Wu (the institute of plasma physics, CAS -ASIPP) Host: Shigeru Morita (the national institute for fusion science -NIFS) Content 1.
More informationModelling of JT-60U Detached Divertor Plasma using SONIC code
J. Plasma Fusion Res. SERIES, Vol. 9 (2010) Modelling of JT-60U Detached Divertor Plasma using SONIC code Kazuo HOSHINO, Katsuhiro SHIMIZU, Tomonori TAKIZUKA, Nobuyuki ASAKURA and Tomohide NAKANO Japan
More informationRadial impurity transport in the H mode transport barrier region in Alcator C-Mod
Radial impurity transport in the H mode transport barrier region in Alcator C-Mod T. Sunn Pedersen, R.S. Granetz, A.E. Hubbard, I.H. Hutchinson, E.S. Marmar, J.E. Rice, J. Terry Plasma Science and Fusion
More informationTungsten: An option for divertor and main chamber PFCs in future fusion devices
ASDEX Upgrade Tungsten: An option for divertor and main chamber PFCs in future fusion devices R. Neu, R. Dux, A. Kallenbach, C.F. Maggi, T. Pütterich, M. Balden, T. Eich, J.C. Fuchs, O. Gruber, A. Herrmann,
More informationFusion Research at the ASDEX Upgrade Tokamak Experiences with Tungsten Plasma Facing Components
Fusion Research at the ASDEX Upgrade Tokamak Experiences with Tungsten Plasma Facing Components Magnetically Confined Fusion Towards ITER Results with Tungsten PFCs in ASDEX Upgrade R. Neu and ASDEX Upgrade
More informationLocal Plasma Parameters and H-Mode Threshold in Alcator C-Mod
PFC/JA-96-42 Local Plasma Parameters and H-Mode Threshold in Alcator C-Mod A.E. Hubbard, J.A. Goetz, I.H. Hutchinson, Y. In, J. Irby, B. LaBombard, P.J. O'Shea, J.A. Snipes, P.C. Stek, Y. Takase, S.M.
More informationLine analysis of EUV Spectra from Molybdenum and Tungsten Injected with Impurity Pellets in LHD
Line analysis of EUV Spectra from Molybdenum and Tungsten Injected with Impurity Pellets in LHD Malay Bikas CHOWDHURI, Shigeru MORITA 1),Motoshi GOTO 1), Hiroaki NISHIMURA 2),Keiji NAGAI and Shinsuke FUJIOKA
More informationDependence of non-local effects on plasma parameters during cold-pulse experiments in Alcator C-Mod
Dependence of non-local effects on plasma parameters during cold-pulse experiments in Alcator C-Mod P. Rodriguez-Fernandez 1, N.M. Cao 1, A. Creely 1, M. Greenwald 1, S. Houshmandyar 2, N.T. Howard 1,
More informationFormation of High-b ECH Plasma and Inward Particle Diffusion in RT-1
J Fusion Energ (2010) 29:553 557 DOI 10.1007/s10894-010-9327-6 ORIGINAL RESEARCH Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1 H. Saitoh Z. Yoshida J. Morikawa Y. Yano T. Mizushima
More informationDevelopment of a High-Speed VUV Camera System for 2-Dimensional Imaging of Edge Turbulent Structure in the LHD
Development of a High-Speed VUV Camera System for 2-Dimensional Imaging of Edge Turbulent Structure in the LHD Masaki TAKEUCHI, Satoshi OHDACHI and LHD experimental group National Institute for Fusion
More information1. Motivation power exhaust in JT-60SA tokamak. 2. Tool COREDIV code. 3. Operational scenarios of JT-60SA. 4. Results. 5.
1. Motivation power exhaust in JT-60SA tokamak 2. Tool COREDIV code 3. Operational scenarios of JT-60SA 4. Results 5. Conclusions K. Gałązka Efficient power exhaust in JT-60SA by COREDIV Page 2 The Institute
More informationMeasurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device
REVIEW OF SCIENTIFIC INSTRUMENTS 76, 053505 2005 Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device K. Ida, a
More informationThe performance of improved H-modes at ASDEX Upgrade and projection to ITER
EX/1-1 The performance of improved H-modes at ASDEX Upgrade and projection to George Sips MPI für Plasmaphysik, EURATOM-Association, D-85748, Germany G. Tardini 1, C. Forest 2, O. Gruber 1, P. Mc Carthy
More informationFlow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes
Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes S. Gangadhara,. Laombard M.I.T. Plasma Science and Fusion Center, 175 Albany St., Cambridge, MA 2139 USA Abstract Accurate
More informationPlasma shielding during ITER disruptions
Plasma shielding during ITER disruptions Sergey Pestchanyi and Richard Pitts 1 Integrated tokamak code TOKES is a workshop with various tools objects Radiation bremsstrahlung recombination s line s cyclotron
More informationBehavior of Compact Toroid Injected into the External Magnetic Field
Behavior of Compact Toroid Injected into the External Magnetic Field M. Nagata 1), N. Fukumoto 1), H. Ogawa 2), T. Ogawa 2), K. Uehara 2), H. Niimi 3), T. Shibata 2), Y. Suzuki 4), Y. Miura 2), N. Kayukawa
More informationS1/2 EX/S, EX/D, EX/W
S1/2 EX/S, EX/D, EX/W S1/2 EX/S - Magnetic Confinement Experiments: Stability 47 papers EX/W - Magnetic Confinement Experiments: Wave plasma interactions, current drive & heating, energetic particles 58
More informationCharacterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod
1 EX/P4-22 Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod Y. Lin, R.S. Granetz, A.E. Hubbard, M.L. Reinke, J.E.
More informationObservation of Tungsten Line Emissions in Wavelength Range of Å in Large Helical Device )
Observation of Tungsten Line Emissions in Wavelength Range of 10-500 Å in Large Helical Device ) Yang LIU 1), Shigeru MORITA 1,2), Tetsutarou OISHI 1,2), Motoshi GOTO 1,2) and Xianli HUANG 2) 1) Department
More informationEffects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal
Effects of stellarator transform on sawtooth oscillations in CTH Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, E.C. Howell, C.A. Johnson, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A.
More informationPlasma impurity composition in Alcator C-Mod tokamak.
Plasma impurity composition in Alcator C-Mod tokamak. I. O. Bespamyatnov a, W. L. Rowan a, K. T. Liao a, M. Brookman a, M. L. Reinke b, E. S. Marmar b, M. J. Greenwald b a Institute for Fusion Studies,
More informationPoloidal Variation of High-Z Impurity Density in ICRF- Heated Alcator C-Mod Plasmas
Poloidal Variation of High-Z Impurity Density in ICRF- Heated Alcator C-Mod Plasmas M.L. Reinke, I.H. Hutchinson, J.E. Rice, N.T. Howard, A. Bader, S. Wukitch, Y. Lin, D.C. Pace, A. Hubbard, J.W. Hughes
More informationRecent Results in Impurity Transport in Tokamaks. D R Mikkelsen PPPL. 2nd Coordinated Working Group Meeting Greifswald, June 4-6, 2007
Recent Results in Impurity Transport in Tokamaks D R Mikkelsen PPPL 2nd Coordinated Working Group Meeting Greifswald, June 4-6, 2007 D. R. Mikkelsen, Coordinated Working Group Meeting, Greifswald, 4-7
More informationSurvey of EUV Impurity Line Spectra and EUV Bremsstrahlung Continuum in LHD )
Plasma and Fusion Research: Regular Articles Volume 6, 2402078 (2011) Survey of EUV Impurity Line Spectra and EUV Bremsstrahlung Continuum in LHD ) Chunfeng DONG, Shigeru MORITA 1), Malay Bikas CHOWDHURI
More informationSpatio-temporal investigations on the triggering of pellet induced ELMs
Spatio-temporal investigations on the triggering of pellet induced ELMs G. Kocsis, S. Kálvin, P.T. Lang*, M. Maraschek*, J. Neuhauser* W. Schneider*, T. Szepesi and ASDEX Upgrade Team KFKI-RMKI, EURATOM
More informationTokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011
Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor
More informationIn-vessel Tritium Inventory in ITER Evaluated by Deuterium Retention of Carbon Dust
FT/P1-19 In-vessel Tritium Inventory in ITER Evaluated by Deuterium Retention of Carbon Dust T. Hino 1), H. Yoshida 1), M. Akiba 2), S. Suzuki 2), Y. Hirohata 1) and Y. Yamauchi 1) 1) Laboratory of Plasma
More informationEffect of ideal kink instabilities on particle redistribution
Effect of ideal kink instabilities on particle redistribution H. E. Ferrari1,2,R. Farengo1, P. L. Garcia-Martinez2, M.-C. Firpo3, A. F. Lifschitz4 1 Comisión Nacional de Energía Atómica, Centro Atomico
More informationInvestigation of Intrinsic Rotation Dependencies in Alcator C-Mod
Investigation of Intrinsic Rotation Dependencies in Alcator C-Mod D. Kwak, A. E. White, J. E. Rice, N. T. Howard, C. Gao, M. L. Reinke, M. Greenwald, C. Angioni, R. M. McDermott, and the C-Mod and ASDEX
More informationPlasma Spectroscopy in ISTTOK
Plasma Spectroscopy in ISTTOK J. Figueiredo 1, R. B. Gomes 1, T. Pereira 1, H. Fernandes 1, A. Sharakovski 2 1 Associação EURATOM/IST, Centro de Fusão Nuclear, IST, 1049-001 Lisboa, Portugal 2 Association
More informationDevelopment of a Lithium Beam Probe and Measurement of Density Pedestal in JT-60U
Development of a Lithium Beam Probe and Measurement of Density Pedestal in JT-60U Atsushi KOJIMA, Kensaku KAMIYA, Takaaki FUJITA, Hirotaka KUBO, Harukazu IGUCHI 1), Naoyuki OYAMA, Takahiro SUZUKI, Yutaka
More informationDiagnostics for Burning Plasma Physics Studies: A Status Report.
Diagnostics for Burning Plasma Physics Studies: A Status Report. Kenneth M. Young Princeton Plasma Physics Laboratory UFA Workshop on Burning Plasma Science December 11-13 Austin, TX Aspects of Plasma
More informationFirst plasma operation of Wendelstein 7-X
First plasma operation of Wendelstein 7-X R. C. Wolf on behalf of the W7-X Team *) robert.wolf@ipp.mpg.de *) see author list Bosch et al. Nucl. Fusion 53 (2013) 126001 The optimized stellarator Wendelstein
More informationEnhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport*
Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport* E. Marmar, B. Lipschultz, A. Dominguez, M. Greenwald, N. Howard, A. Hubbard, J. Hughes, B. LaBombard, R. McDermott, M. Reinke,
More informationLower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation
Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation P.T. Bonoli, A. E. Hubbard, J. Ko, R. Parker, A.E. Schmidt, G. Wallace, J. C. Wright, and the Alcator C-Mod
More informationDesign of New Optical System for Visible Plasma Radiation Measurements at COMPASS Tokamak
WDS'08 Proceedings of Contributed Papers, Part II, 100 104, 2008. ISBN 978-80-7378-066-1 MATFYZPRESS Design of New Optical System for Visible Plasma Radiation Measurements at COMPASS Tokamak D. I. Naydenkova
More informationDivertor Requirements and Performance in ITER
Divertor Requirements and Performance in ITER M. Sugihara ITER International Team 1 th International Toki Conference Dec. 11-14, 001 Contents Overview of requirement and prediction for divertor performance
More informationAdvancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment
Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment E. T. Hinson J. L. Barr, M. W. Bongard, M. G. Burke, R. J. Fonck, J. M. Perry, A. J. Redd,
More informationPlasma Radiation. Ø Free electrons Blackbody emission Bremsstrahlung
Plasma Radiation Ø Free electrons Blackbody emission Bremsstrahlung Ø Bound electrons (Z>2) Unresolved, multi-line emission Resolved line emission -- Single Z +n Objective Infer a thermodynamic quantity
More informationInitial Experimental Program Plan for HSX
Initial Experimental Program Plan for HSX D.T. Anderson, A F. Almagri, F.S.B. Anderson, J. Chen, S. Gerhardt, V. Sakaguchi, J. Shafii and J.N. Talmadge, UW-Madison HSX Plasma Laboratory Team The Helically
More informationCharacterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment
Characterization of Edge Stability and Ohmic H-mode in the PEGASUS Toroidal Experiment M.W. Bongard, J.L. Barr, M.G. Burke, R.J. Fonck, E.T. Hinson, J.M. Perry, A.J. Redd, D.J. Schlossberg, K.E. Thome
More informationNoninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE
1 EX/P6-18 Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE M. Uchida, T. Maekawa, H. Tanaka, F. Watanabe, Y.
More informationD.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706
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 Concept Overview Implementation on PEGASUS Results Current
More informationThis work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract
This work was performed under the auspices of the U.S. Department of Energy by under contract DE-AC52-7NA27344. Lawrence Livermore National Security, LLC The ITER tokamak Tungsten (W) is attractive as
More informationAlcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139
Alcator C-Mod Double Transport Barrier Plasmas in Alcator C-Mod J.E. Rice for the C-Mod Group MIT PSFC, Cambridge, MA 139 IAEA Lyon, Oct. 17, Outline Double Barrier Plasma Profiles and Modeling Conditions
More informationDeuterium Balmer/Stark spectroscopy and impurity profiles: first results from mirror-link divertor spectroscopy system on the JET ITER-like wall
CCFE-PR(13)35 A.G. Meigs, S. Brezinsek, M. Clever, A. Huber, S. Marsen, C. Nicholas, M.Stamp, K-D Zastrow, and JET EFDA Contributors Deuterium Balmer/Stark spectroscopy and impurity profiles: first results
More informationPredicting the Rotation Profile in ITER
Predicting the Rotation Profile in ITER by C. Chrystal1 in collaboration with B. A. Grierson2, S. R. Haskey2, A. C. Sontag3, M. W. Shafer3, F. M. Poli2, and J. S. degrassie1 1General Atomics 2Princeton
More informationTangential SX imaging for visualization of fluctuations in toroidal plasmas
Tangential SX imaging for visualization of fluctuations in toroidal plasmas S. Ohdachi,, K. Toi, G. Fuchs and the LHD Experimental Group National Institute for Fusion Science Outline of my talk 1. Merit
More informationTungsten Screening and Impurity Control in JET
1 EX/P3-15 Tungsten Screening and Impurity Control in JET T. Pütterich 1, R Dux 1, M.N.A. Beurskens 2, V. Bobkov 1, S. Brezinsek 3, J. Bucalossi 4, J.W. Coenen 3, I. Coffey 5, A. Czarnecka 6, C. Giroud
More informationCurrent Drive Experiments in the Helicity Injected Torus (HIT II)
Current Drive Experiments in the Helicity Injected Torus (HIT II) A. J. Redd, T. R. Jarboe, P. Gu, W. T. Hamp, V. A. Izzo, B. A. Nelson, R. G. O Neill, R. Raman, J. A. Rogers, P. E. Sieck and R. J. Smith
More informationICRF Induced Argon Pumpout in H-D Plasmas at Alcator C-Mod
0 ICRF Induced Argon Pumpout in H-D Plasmas at Alcator C-Mod C Gao J.E. Rice, M.L. Reinke, S.J. Wukitch, Y. Lin and Alcator C-Mod Team MIT-PSFC October 29, 2014 C Gao etc., MIT-PSFC 56th APS-DPP New Orleans,
More informationGeneration and Characterization of High Heat-Flux Plasma-Flow for Divertor Simulation Studies Using a Large Tandem Mirror Device
1 FTP/P1-33 Generation and Characterization of High Heat-Flux Plasma-Flow for Divertor Simulation Studies Using a Large Tandem Mirror Device * Y. Nakashima 1), I. Katanuma 1), K. Hosoi 1), H. Ozawa 1),
More informationInformation Session for the ITER CPTS System
Information Session for the ITER CPTS System Fusion for Energy Barcelona, 15 April 2015 1 Introduction to the meeting Information provided is preliminary and subject to Agenda change ahead of formal tendering
More informationComparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak
Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak T.C. Jernigan, L.R. Baylor, S.K. Combs, W.A. Houlberg (Oak Ridge National Laboratory) P.B. Parks (General
More informationObservations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas
1 EX/P5-4 Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas J.E. Rice 1), A.C. Ince-Cushman 1), P.T. Bonoli 1), M.J. Greenwald 1), J.W. Hughes 1), R.R. Parker 1), M.L. Reinke
More information2017 US/EU Transport Task Force Workshop April 26 th 2017 Williamsburg, VA
Pablo Rodriguez-Fernandez 1, A. E. White 1, N. M. Cao 1, A. J. Creely 1, M. J. Greenwald 1, N. T. Howard 1, A. E. Hubbard 1, J. W. Hughes 1, J. H. Irby 1, C. C. Petty 2, J. E. Rice 1 1 Plasma Science and
More informationHFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION
ASDEX Upgrade Session: "Issues and prospects of effcient fueling for magnetic confinement" HFS ELLET REFUELING FOR HIGH DENSITY TOKAMAK OERATION.T. Lang for the ASDEX Upgrade and JET teams Cubic mm size
More information- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -
15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect
More informationProspects of Nuclear Fusion Energy Research in Lebanon and the Middle-East
Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East Ghassan Antar Physics Department American University of Beirut http://www.aub.edu.lb/physics/lpfd Outline 1. Introduction and
More informationTHE DIII D PROGRAM THREE-YEAR PLAN
THE PROGRAM THREE-YEAR PLAN by T.S. Taylor Presented to Program Advisory Committee Meeting January 2 21, 2 3 /TST/wj PURPOSE OF TALK Show that the program plan is appropriate to meet the goals and is well-aligned
More informationNIST Research on Spectroscopy and Collisional-Radiative Modeling of Highly-Charged Ions of Tungsten
NIST Research on Spectroscopy and Collisional-Radiative Modeling of Highly-Charged Ions of Tungsten Yuri Ralchenko National Institute of Standards and Technology Gaithersburg, USA Vienna, Austria, Dec
More informationR&D Status of KSTAR Soft X-ray Tomographic Array Diagnostic System
R&D Status of KSTAR Soft X-ray Tomographic Array Diagnostic System Seung Hun Lee, Junghee Kim, and W. Choe Department of Physics KAIST (Korea Advanced Institute of Science and Technology) JA-KO Joint Workshop
More informationTungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER
Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER The MIT Faculty has made this article openly available. Please share how this access
More informationPhysics of fusion power. Lecture 14: Anomalous transport / ITER
Physics of fusion power Lecture 14: Anomalous transport / ITER Thursday.. Guest lecturer and international celebrity Dr. D. Gericke will give an overview of inertial confinement fusion.. Instabilities
More informationSummary of CDBM Joint Experiments
11th Meeting of the ITPA CDBM TG, Chengdu, 23-24 Oct. 2006 Summary of CDBM Joint Experiments Mon. 23 Oct, morning T. Takizuka (JAEA) CDB-2: Confinement scaling in ELMy H-modes; β degradation C.C. Petty
More informationC-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center
C-Mod Core Transport Program Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center Practical Motivations for Transport Research Overall plasma behavior must be robustly
More informationSTEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U
Abstract STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-6U A. SAKASAI, H. TAKENAGA, N. HOSOGANE, H. KUBO, S. SAKURAI, N. AKINO, T. FUJITA, S. HIGASHIJIMA, H. TAMAI, N. ASAKURA, K. ITAMI,
More informationKSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta
1 THS/P2-05 KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta Y.S. Park 1), S.A. Sabbagh 1), J.W. Berkery 1), J.M. Bialek 1), Y.M. Jeon 2), S.H. Hahn 2), N. Eidietis
More informationH-mode and ELM Dynamics Studies at Near-Unity Aspect Ratio in the PEGASUS Toroidal Experiment and their Extension to PEGASUS-Upgrade. M.W.
H-mode and ELM Dynamics Studies at Near-Unity Aspect Ratio in the PEGASUS Toroidal Experiment and their Extension to PEGASUS-Upgrade M.W. Bongard J.L. Barr, G.M. Bodner, M.G. Burke, R.J. Fonck, H.G. Frerichs,
More informationStatus of Design and R&D for the Korean ITER Diagnostic Systems
1 ITR/P1-04 Status of Design and R&D for the Korean ITER Diagnostic Systems H.G. Lee 1), S. Pak 1), M.S. Cheon 1), C.R. Seon 1), S.H. Choi 1), H.K. Park 2), Y.S. Hwang 3), R. Barnsley 4), L. Bertalot 4),
More informationAnalyses of Visible Images of the Plasma Periphery Observed with Tangentially Viewing CCD Cameras in the Large Helical Device
Analyses of Visible Images of the Plasma Periphery Observed with Tangentially Viewing CCD Cameras in the Large Helical Device M. SHOJI, T. WATANABE, S. MASUZAKI, H. YAMADA, A. KOMORI and LHD Experimental
More informationPlasma Wall Interactions in Tokamak
Plasma Wall Interactions in Tokamak Dr. C Grisolia, Association Euratom/CEA sur la fusion, CEA/Cadarache Outline 1. Conditions for Fusion in Tokamaks 2. Consequences of plasma operation on in vessel materials:
More informationExhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France
Exhaust scenarios Alberto Loarte Plasma Operation Directorate ITER Organization Route de Vinon sur Verdon, 13067 St Paul lez Durance, France Acknowledgements: Members of ITER Organization (especially R.
More informationResistive Wall Mode Observation and Control in ITER-Relevant Plasmas
Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas J. P. Levesque April 12, 2011 1 Outline Basic Resistive Wall Mode (RWM) model RWM stability, neglecting kinetic effects Sufficient for
More informationReduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection
Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection M. Porkolab, P. C. Ennever, S. G. Baek, E. M. Edlund, J. Hughes, J. E.
More informationProgress in characterization of the H-mode pedestal
Journal of Physics: Conference Series Progress in characterization of the H-mode pedestal To cite this article: A W Leonard 2008 J. Phys.: Conf. Ser. 123 012001 View the article online for updates and
More informationOVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center
OVERVIEW OF THE ALCATOR C-MOD PROGRAM IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OUTLINE C-Mod is compact, high field, high density, high power
More informationPlasma and Fusion Research: Regular Articles Volume 10, (2015)
Possibility of Quasi-Steady-State Operation of Low-Temperature LHD-Type Deuterium-Deuterium (DD) Reactor Using Impurity Hole Phenomena DD Reactor Controlled by Solid Boron Pellets ) Tsuguhiro WATANABE
More informationControl of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal
Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A. Roberds,
More informationDIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH
DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK
More informationD.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706
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 Non-solenoidal startup using point-source DC helicity injectors
More informationIon Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device
Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Kenichi NAGAOKA, Masayuki YOKOYAMA, Yasuhiko TAKEIRI, Katsumi IDA, Mikiro YOSHINUMA, Seikichi MATSUOKA 1),
More informationDrift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer
Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer N. Smick, B. LaBombard MIT Plasma Science and Fusion Center PSI-19 San Diego, CA May 25, 2010 Boundary flows
More informationFormation and stability of impurity snakes in tokamak plasmas
PSFC/JA--9 Formation and stability of impurity snakes in tokamak plasmas L. Delgado-Aparicio,, L. Sugiyama, R. Granetz, J. Rice, Y. Podpaly, M. Reinke, D. Gates, P. Beirsdorfer 4, M. Bitter, S. Wolfe,
More informationFirst Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas
1 PD/1-1 First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas R. Nazikian 1, W. Suttrop 2, A. Kirk 3, M. Cavedon 2, T.E. Evans
More informationProgress of Confinement Physics Study in Compact Helical System
1st IAEA Fusion Energy Conference Chengdu, China, 16-1 October, 6 IAEA-CN-149/ EX/5-5Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS-839 Oct. 6 1 EX/5-5Rb Progress
More informationTHE ADVANCED TOKAMAK DIVERTOR
I Department of Engineering Physics THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and the team 14th PSI QTYUIOP MA D S O N UCLAUCLA UCLA UNIVERSITY OF WISCONSIN THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and
More information