INTERNAL TRANSPORT BARRIER THRUST
|
|
- Denis Dixon
- 6 years ago
- Views:
Transcription
1 INTERNAL TRANSPORT BARRIER THRUST by C.M. Greenfield Presented to Program Advisory Committee Meeting January, 3 /TST/wj
2 THE GOAL OF THRUST 7 IS TO ESTABLISH CONTROL OVER THE INTERNAL TRANSPORT BARRIER Increase spatial extent of barrier. Increased fusion performance. Control pressure gradient in barrier. Avoid MHD instabilities which can terminate ITB or disrupt discharge..5 a.u MHD limits.5 a.u. Counter-NBI Neon puffing Off-axis ECH Off-axis pellets Off-axis NBI.. Maintain elevated/reversed q profile. Avoid MHD instabilities when q min. Impacts ITB characteristics, especially in n e and T e profiles. Take advantage of favorable impact of counter-nbcd and bootstrap currents in broadened barriers. Improved stability.5 a.u. local p... Counter-NBI Modulated off-axis ECH Neon injection ITB Improved fusion performance?.6 a.u... Greenfield DAC
3 THRUST 7 EXPERIMENTS PERFORMED IN 999 Large qmin produced with fast current ramp and early, high power NB heating. No fixed relationship between details of the q profile and the ITB location identified. Counter-NBI conditioning and discharge development. Customers included RWM thrust, Confinement TSA and Heating and Current drive TSA. Impurity transport with counter-nbi. Particle source may be enhanced, but inward transport is not. Develop fast-ion free preheat using ECH. Produced NCS profiles similar to those using early beams. Electron transport barrier result shown in Confinement TSA talk result of this experiment. ITB formation and expansion with counter-nbi. Steady ELMless H mode shown in Confinement TSA talk from late in these discharges. ITB formation triggered by pellet injection. Greenfield DAC 3
4 COUNTER NEUTRAL BEAM INJECTION ALLOWS ACCESS TO NEW REGIONS OF PARAMETER SPACE Standard recipe for internal transport barrier (ITB) formation in uses co-nbi (neutral beam injection parallel to the plasma current) applied early during the current ramp. ITB forms near magnetic axis at very low power. Fundamental limit to sustainment occurs when q min reaches unity. TFTR, JT 6U both report best performance with balanced or counter-nbi. However, these devices exhibit a power threshold. Recent experiment exploit the advantages of counter NBI. Counter neutral beam CD maintain an elevated q profile. Alignment of pressure gradient and rotation terms of the E B shearing rate is favorable with counter-nbi except near the magnetic axis. Greenfield DAC 4
5 99849 (.7s): Counter-NBI W =.9 MJ P NBI =. MW (6.5 MW absorbed). COUNTER-NBI RESULTS IN BROADER PROFILES kev 5 5 T e counter co T i 9 m n e 873 (.8s): Co-NBI W =. MJ P NBI = 9.6 MW (7.6 MW absorbed). 5 s - 3 Ω 6 4 q Greenfield DAC 5
6 COMBINATION OF p AND ROTATION EFFECTS IN ω E B NATURALLY BROADENS COUNTER BARRIERS Shearing rate ω E B separated into thermal main ion rotation and pressure gradient terms. Total calculated from CER impurity measurements. Main ion pressure term from profile measurements. Rotation term by subtraction. Stability to drift ballooning modes calculated using a linear gyrokinetic stability (GKS) code. Non-circular, finite aspect ratio equilibria with fully electromagnetic dynamics. With counter-nbi: Linear growth rates smaller at at large, possibly due to higher Z eff near edge (core Z eff ª.5 in both cases). Shearing rate profile extends to larger. 5 s s (co) s (counter) s ω E B p ω E B rotation ω E B co (873.8s) ctr ( s) 4 ω E B ω E B γ max p ω E B rotation ω E B Greenfield DAC 6
7 5 4 IMPURITIES DO NOT PREFERENTIALLY BUILD UP NEAR THE MAGNETIC AXIS DURING AN ITB OF LIMITED DURATION co-nbi counter-nbi Zeff 3.6s.7s.8s.97s.7s.7s Z eff constant in the vicinity of the magnetic axis during ITB evolution. Counter-NBI results in little or no additional core accumulation. Significant impurity buildup near edge with counter-nbi. Greenfield DAC 7
8 DIII-D Pellet Injection Program Modifications to injector (that was installed on JET 987-9): All three guns fire.7 mm pellets Punch mechanism on one gun to reliably generate slower pellets (< m/s) Second gun has oversized barrel that allows moderate speed pellets independent guide tubes on inner wall (HFS) - one on midplane, one at 45 degrees - and one vertical. Can be connected to any of the pellet guns or a gas valve. Performance tests were performed on curved guide tubes. Initial experiments on the vertical injection port were performed in 998 and on the HFS ports in March-June 999. Aug LRB Greenfield DAC 8
9 PELLETS INJECTED FROM THE HIGH FIELD SIDE DURING THE CURRENT RAMP CAN FORM AN INTERNAL TRANSPORT BARRIER MW 9 m <n e > P NBI H 89 Pellets () kev 9 m n e s (no pellet) T e 9978.s (PEP) T i.5..5 time (s) mm pellets injected during current rise from the new high-field-side guide tube produces peaked density profile for ITB studies with T i ª T e. MW of counter-nbi applied to produce ITB in L mode. Greenfield DAC 9
10 THRUST 7 PLAN FOR The three-day plan will continue our attempts to address both expansion and pressure gradient control using counter-nbi. Optimization of Counter-NBI Generated ITBs ( days). Due to time constraints, we plan a limited attempt at exploration with one additional tool (TBD): Neon puffing to improve ITB (First of days). Off-axis ECH to expand radius of ITB ( day). Note that due to similar machine requirements, the transition from one experiment to the next may not be made at the beginning of a day. No explicit pellet experiments, but barriers triggered both with and without pellets may be included in experiments. An additional two days, if available, would be used to complete the above experiments. Greenfield DAC
11 OPTIMIZATION OF COUNTER-NBI GENERATED ITB ( DAYS) Background ITBs formed with counter-nbi, with (in at least some cases) nearly stationary q profiles. We did not have time to attempt barrier expansion and control. Proposed experiment Reestablish ITB with power stepdown. Ramp up neutral beam power (using PCS modulation). Scan ramp rate for optimum barrier growth without disruption. After barrier growth is established, reduce beam power later in discharge to attempt a steady phase. If successful, we can move on to a neutral beam feedback control attempt. What do we use as a feedback signal: neutron rate, stored energy, Er? MA MW 5 s I P S N P ECH (6 sources) (6 4 sources) (6 5 sources) 9986 (6 4 5 sources) P NBI time (s) Greenfield DAC
12 NEON IMPURITY INJECTION Reduced transport is a common feature of discharges with impurity injection (ISX B, Textor, JET,, ). Identified with decreased core fluctuations and calculated linear turbulence growth rates. Standard feedback loop: E B shearing rate increases as barrier forms. Improved energy (H89 ) and particle confinement. Produces broad ITBs with easily maintained L mode edge and lower Ti / Te. Previous experiments concentrated at low power and density and high q95. Remaining challenges: Access at low q95. Can elevated q profile be maintained? Feedback control of radiated power? Can low Zeff be maintained? Extensive modeling in progress to guide experimental development. T i (kev) Ion Temperature Profile t=.6 sec..4 χ i (m /s) Minor Radius () Neon Reference.8. χ i (=.65) Toroidal Rotation (rad/s).5x TIME (s).. no neon neon (.4V) neon (.8V) Carbon Rotation Profile t=.6 sec Minor Radius () Neon Reference. Greenfield DAC
13 EXPERIMENTS USING NEON INJECTION WILL OPTIMIZE AND CHARACTERIZE THE IMPACT OF IMPURITY-IMPROVED TRANSPORT Variation of impurity puff. Attempt feedback control of neon injection and pumping to control p rad and n e. Use neon as trigger in short burst, attempt to maintain ITB with E B shear. Attempt to use helium (lower Z) or nitrogen (better pumping?) as the impurity. Variation of q profile. Decrease q 95, either by increasing toroidal field or decreasing plasma current. Apply counter ECCD and/or counter NBCD to maintain elevated q profile. Variation of heating. Increase heating power. Momentum scan (reduce beam voltage at constant power). Increase density (gas puffing or HFS pellet injection). Use puff N pump to maintain higher concentration of impurity at edge. Greenfield DAC 3
14 Background Application of on-axis ECH increases transport in all channels. Transport in the ITB can become too good, becoming a challenge to MHD stability. Tools to make the barrier leaky may be desirable (AT Workshop). ECH may be a useful tool to limit the pressure gradient in the presence of an ITB, thereby extending the duration. ECH (heating) to limit or move ITB 9 kev/m 3 MW/m 3 4 A B C (a) Electron Pressure (c) 9 kev/m 3 A B C (b) Ion Pressure ECH Power Ion Thermal Density. B Diffusivity B C C A...4 r/a.8..4 r/a.8 m /s 8 4 (d) Control ITB position: Heating outside barrier predicted to cause barrier to move toward heating location expansion (Staebler). Control ITB strength: Modulated heating inside/outside barrier should regulate strength of gradient (Newman). Electron temperature (times 5eV) no transition and no perturbation transition and perturbation transition and no perturbation r/a Greenfield DAC 4
15 THRUST 7 GOALS FOR AND BEYOND Short term goal: : Open-loop tests of potential control mechanisms. Counter-NBI (started in 999). - Neon injection: combine previous results (G. McKee, APS invited talk, 999) with ITB techniques to extend good confinement region. Off-axis ECH to control barrier strength and position. -? Off-axis pellet injection. Barrier expansion through modification of rotation profile. Magnetic braking. Simulate successful balanced injection condition (TFTR, JT-6U) by using magnetic braking to remove momentum. Off-axis NBI. Broader heating profiles theoretically and experimentally (JT-6U) shown to broaden barrier. Target q profile modification with ECH/ECCD. Greenfield DAC 5
16 THRUST 7 GOALS FOR AND BEYOND (continued) Short term goals, continued All were proposed for, but limited time (three days) allows only the first -3 tools to be tested this year. Depending on future experimental time availability, may take -3 years to do all experiments. Longer term goal: Apply feedback control of promising (based on closed-loop tests) mechanisms to produce barriers with large spatial extent and gradients maintained below stability limits. Not necessarily synchronous with open-loop tests. Greenfield DAC 6
17 THRUST 7 EXPERIMENTS ADDRESS FESAC GOALS, AND 3 Advance fundamental understanding of plasma, the fourth state of matter, and enhance predictive capabilities, through comparison of experiments, theory and simulation. Core barriers provide a test bed for enhancing our understanding of turbulence and transport, as well as mechanisms which may reduce transport, including E B flow shear. These experiments allow us to probe these phenomena in more detail by changing the relationship of individual terms in the shearing rate as well as the instability growth rates. Interpretation of the results is done in active collaboration with the theory and modeling community, thus fostering comparison of experiments, theory and simulation. Resolve outstanding scientific issues and establish reduced-cost paths to more attractive fusion energy systems by investigating a broad range of innovative magnetic confinement configurations. Transport barrier control identified as key scientific issue at AT Workshop and Snowmass. Advance innovation and understanding in high-performance plasmas, optimizing for projected power-plant requirements; and participate in a burning plasma experiment. Improved understanding and control of core barriers is important for optimization of AT scenarios. Greenfield DAC 7
18 THRUST 7 EXPERIMENTS HAVE INCREASED OUR UNDERSTANDING AND CONTROL OF TRANSPORT BARRIERS FORMATION of internal transport barriers Appearance of ITB formation power threshold with counter NBI may be related to interplay between p and rotation terms of the E B shearing rate near magnetic axis. Pellets trigger formation of core barriers with T i ª T e. EXPANSION of the internal transport barrier Broader ITB produced with counter-nbi. Except in the vicinity of the magnetic axis, the pressure gradient and rotation terms of the E B shearing rate add, rather than cancel (as in co-nbi cases). Increased or broadened pressure profile aids E B shear stabilization of microturbulence. Broadened heating profiles may also impact barrier dynamics. Thrust 7 results were reported in two invited talks at the APS-DPP conference in Seattle: C.M. Greenfield, Understanding and Control of Transport in Advanced Tokamak Regimes in, paper BI. L.R. Baylor, Improved Core Fueling with Pellets Injected from the High Field Side of the Tokamak, paper UI 4. Greenfield DAC 8
19 Additional slides
20 ITB FORMATION EXHIBITS POWER THRESHOLD WITH COUNTER-INJECTION Co-NBI: ITB forms with P NBI.5 MW and e xpands with P NBI 5 MW. Counter-NBI: Clear barriers formed only with P NBI ~9 MW. Beam power losses occur in both co- and counter-nbi discharges. ~% lost for co-injection Shinethrough and charge exchange. ~3-4% with counter-injection. Additional beam ion orbit losses. Difference between co and counter beam ion losses is too small to explain observed increase in threshold power. Threshold power similar to that in TFTR balanced injection at similar toroidal field. Greenfield DAC
21 CORE FLUCTUATIONS ARE REDUCED IN THE PRESENCE OF THE ITB T i (CER) Barrier begins forming soon after onset of high power neutral beam heating. No TFTR-like E r precursor seen. kev 8 4 χ i =.6 ELMing H mode phase interrupts ITB after MHD activity releases energy from core. m /s.. =.3 Core fluctuations drop following H L transition, in conjunction with ITB reformation. Profiles indicate resumption of ITB development. MW..5 BES δi/i (%) k θ cm - ( ms averaging) P ECH P NBI I P t (sec) D α (a.u.).6.4 MA Greenfield DAC
22 χ e THE REDUCED TRANSPORT REGION IS BROADER IN ALL CHANNELS WITH COUNTER-NBI χ i..8 Ion heating power m /s W/cm D e counter ( s) co (873.8s). χ ϕ χ neo i m /s.. Possible causes of ITB broadening: Broader heating profile Enhanced E B shear Greenfield DAC
23 PELLETS CAN BE USED TO TRIGGER ITB FORMATION WITH DIFFERENT BARRIER CHARACTERISTICS Both deuterium and lithium pellets have been used to trigger formation of the ITB. No power threshold observed, even with counter-nbi. Similar to observations in other devices (JET, TFTR, ) Similar to PEP regimes previously observed in other devices. Barriers exhibit high gradients in both the density and temperature profiles. Lower temperatures and higher densities observed. T i / T e ª.5, much lower than observed with neutral beams alone. Greenfield DAC 3
24 STATIONARY CENTRAL q PROFILES MAINTAINED BY COUNTER NEUTRAL BEAM CURRENT DRIVE.4 co-nbi counter-nbi..7s.6s..8s.97s.7s.8.7s.6 During ms period leading up to peak parameters: Co-NBI: q profile evolution accelerates. Counter-NBI: q profile evolution decelerates, becomes stationary with fully developed ITB. Counter-NBI provides central counter-current drive, which can maintain an elevated q profile. Alleviates an eventual limitation to ITB performance, as barrier terminates as q min Greenfield DAC 4
Magnetohydrodynamics (MHD) III
Magnetohydrodynamics (MHD) III Yong-Su Na National Fusion Research Center POSTECH, Korea, 8-10 May, 2006 Review II 1. What is Stability? 2. MHD Instability Interchange Mode Flux Tube Instabilities 3. Formulation
More informationHigh-Radiation and High-Density Experiments in JT-60U
High-Radiation and High-Density Experiments in JT-6U H. Kubo, S. Sakurai, N. Asakura, S. Konoshima, H. Tamai, S. Higashijima, A. Sakasai, H. Takenaga, K. Itami, K. Shimizu, T. Fujita, Y. Kamada, Y. Koide,
More informationRecent Results and Plans for the Advanced Tokamak Program
Recent Results and Plans for the Advanced Tokamak Program Program Advisory Committee Review February 6-7, 2002 MIT PSFC Presented by A. Hubbard Outline Overview Results from 2001and plans for 2002 - Internal
More informationGA A26763 CONFINEMENT AND PEDESTAL CHARACTERISTICS IN H-MODE WITH ECH HEATING
GA A26763 CONFINEMENT AND PEDESTAL CHARACTERISTICS by R. PRATER, J.S. degrassie, P. GOHIL, T.H. OSBORNE, E.J. DOYLE, and L. ZENG MAY 2010 DISCLAIMER This report was prepared as an account of work sponsored
More informationDevelopment of Advanced Operation Scenarios in Weak Magnetic-Shear Regime on JT-60U
EX/1-4Rc Development of Advanced Operation Scenarios in Weak Magnetic-Shear Regime on JT-60U T. Suzuki 1), N. Oyama 1), A. Isayama 1), Y. Sakamoto 1), T. Fujita 1), S. Ide 1), Y. Kamada 1), O. Naito 1),
More informationProgress report for the MHD Physics Working Group (P3) Ted Strait and Chris Hegna July 12, 2002
Progress report for the MHD Physics Working Group (P3) Ted Strait and Chris Hegna July 12, 2002 Broad questions for the MHD working group What limitations will MHD instabilities impose on the ability of
More informationRapid Pedestal Pressure Increase in High Triangularity, Double-Null QH-mode Discharges
Rapid Pedestal Pressure Increase in High Triangularity, Double-Null QH-mode Discharges by K.H. Burrell with X. Chen, A.M. Garofalo, G.R. McKee, C.M. Muscatello, T.H. Osborne, T.L. Rhodes, P.B. Snyder,
More informationPlasma Fueling and Implications for FIRE, ITER, ARIES
Plasma Fueling and Implications for FIRE, ITER, ARIES M. J. Gouge Oak Ridge National Laboratory March 6, 2001 MJG:TTM, 3/01 1 Outline Fueling system functions Fueling program scope ITER and FIRE fueling
More informationEX/9-1 Progress in Preparing Scenarios for ITER Operation
EX/9-1 Progress in Preparing Scenarios for ITER Operation George Sips (JET-EFDA, UK) G. Giruzzi, S. Ide, C. Kessel, T. Luce, J. Snipes, J. Stober For the IOS-TG of the ITPA FEC 2014, St Petersburg, Russia
More informationITER R&D Needs, Challenges, and the Way Forward
ITER R&D Needs, Challenges, and the Way Forward Bernard Bigot Director General ITER Organization, Cadarache, France Fusion Power Co-ordinating Committee Mtg, IO Headquarters, 24 Jan 2018 1 Context of ITER
More informationDisruption mitigation with high-pressure noble gas injection
Disruption mitigation with high-pressure noble gas injection D. G. Whyte*, University of California San Diego T.C. Jernigan, Oak Ridge National Laboratory D.A. Humphreys, A.W. Hyatt, T.E. Evans, P.B. Parks,
More informationFueling Requirements for Steady State Spherical Torus Operation
Supported by Fueling Requirements for Steady State Spherical Torus Operation Roger Raman, Thomas R. Jarboe, + Henry W. Kugel University of Washington, Seattle + Princeton Plasma Physics Laboratory Joint
More informationDisruption Science Issues and Opportunities for a Burning Plasma Science Experiment
Disruption Science Issues and Opportunities for a Burning Plasma Science Experiment Prepared and presented by: John Wesley General Atomics San Diego, California With recent disruption science results and
More informationPerspectives on Burning Plasma Research
Perspectives on Burning Plasma Research Charles M. Greenfield, Director Amanda E. Hubbard, Deputy Director US Burning Plasma Organization National Academies Burning Plasma Committee June 5, 2017 This work
More information4 JET Studies. 4 JET Studies 4.1 INTRODUCTION
4.1 INTRODUCTION JET has been in shutdown for the whole of the year to install the ITER-Like Wall (ILW) and to complete the major neutral beam enhancement and a suite of diagnostic changes and improvements.
More informationITER contributions to closing DEMO physics gaps
ITER contributions to closing DEMO physics gaps SD Pinches, DJ Campbell, Y Gribov, GTA Huijsmans, S-H Kim, M Lehnen, A Loarte, JA Snipes, G de Temmerman Science & Operations Department, ITER Organization
More informationMagnetic Confinement Fusion: Progress and Recent Developments
Magnetic Confinement Fusion: Progress and Recent Developments Howard Wilson, Dept Physics, University of York, Heslington, York YO10 5DD With thanks to A Field, K Gibson and A Kirk howard.wilson@york.ac.uk
More informationFueling Technology for Disruption & VDE Mitigation
Fueling Technology for Disruption & VDE Mitigation ORNL Fueling Group [Gouge, Foster, Fisher, Jernigan, Baylor, et al.] Oak Ridge National Laboratory Burning Plasma Workshop May 1-3, 2001 MJG/PWF/NAU,
More informationGA A25839 HIGH PERFORMANCE PLASMA OPERATION ON DIII-D DURING EXTENDED PERIODS WITHOUT BORONIZATION
GA A25839 HIGH PERFORMANCE PLASMA OPERATION ON DIII-D DURING EXTENDED PERIODS WITHOUT BORONIZATION by W.P. WEST, M. GROTH, A.W. HYATT, G.L. JACKSON, M.R. WADE, C.M. GREENFIELD, and P.A. POLITZER JULY 2007
More informationNon-linear MHD modelling of pellet injection for ELM control in ITER. Technical Specifications
Non-linear MHD modelling of pellet injection for ELM control in ITER Technical Specifications Table of Contents 1 PURPOSE 3 2 SCOPE 3 3 DEFINITIONS 5 4 REFERENCES 5 5 ESTIMATED DURATION 5 6 WORK DESCRIPTION
More informationDisruptions in ITER: Major Catastrophe or Minor Annoyance? Sarah Angelini April 21, 2011
Disruptions in ITER: Major Catastrophe or Minor Annoyance? Sarah Angelini April 21, 2011 Disruptions Types of Disruptions Time Scales from the IDDB Thermal Quench Current Quench DINA Simulation Results
More informationSimulation of Power Exhaust in Edge and Divertor of the SlimCS Tokamak Demo Reactor
J. Plasma Fusion Res. SERIES, Vol. 9 (2010) Simulation of Power Exhaust in Edge and Divertor of the SlimCS Tokamak Demo Reactor Nobuyuki ASAKURA, Katsuhiro SHIMIZU, Hisato KAWASHIMA, Kenji TOBITA and Tomonori
More informationFTU: Experimental Results and Prospects
FTU: Experimental Results and Prospects C Gormezano ENEA Frascati Frascati Tokamak Upgrade is a high field, high density experiment: a=0.3m, R=0.93m, limiter machine Bt up to 8T, Ip up to 1.6MA. Additional
More informationLong term renovation inside KSTAR vacuum vessel toward steady state operation
IAEA SSO Long term renovation inside KSTAR vacuum vessel toward steady state operation Jong-Gu Kwak, S.W. Jung, S.G. Kim, J.H. Kim, D.R. Lee K-DEMO On behalf of KSTAR team NFRI, Korea KSTAR ITER Near term(~2021)
More informationGA A27249 EXPERIMENTAL TESTS OF STIFFNESS IN THE ELECTRON AND ION ENERGY TRANSPORT IN THE DIII-D TOKAMAK
GA A27249 EXPERIMENTAL TESTS OF STIFFNESS IN THE ELECTRON AND ION ENERGY TRANSPORT IN THE DIII-D TOKAMAK by T.C. LUCE, K.H. BURRELL, J.C. DeBOO, J.E. KINSEY, A. MARINONI, C.C. PETTY, E.J. DOYLE, C. HOLLAND,
More informationIntegrated Scenarios: Advanced Regimes
Integrated Scenarios: Advanced Regimes Program Advisory Committee Meeting February 6-8, 2008 MIT PSFC Presented by A. Hubbard, for the Advanced Scenarios thrust group Outline Scope and niche of Advanced
More informationEAST(HT-7U ) Physics and Experimental Plan
EAST(HT-7U ) Physics and Experimental Plan EAST team, presented by Jiangang Li Institute of Plasma Physics, CAS 1 st EAST IAC meeting Hefei, Oct.10-11 The mission of EAST To explore the methods to achieve
More informationPlasma Research Center, University of Tsukuba Y. Nakashima, GAMMA 10 Group
14th US-Japan Workshop on Inertial Electrostatic Confinement Fusion University of Maryland, College Park College Park, MD October 14th - 17th, 2012 The GAMMA 10 Tandem Mirror Plasma Confinement Device
More informationGas Jet Disruption Mitigation Studies on Alcator C-MOD
Gas Jet Disruption Mitigation Studies on Alcator C-MOD R. Granetz 1, D. Whyte 2, V. Izzo 1, T. Biewer 1, M. Reinke 1, J. Terry 1, A. Bader 1, M. Bakhtiari 2, T. Jernigan 3, G. Wurden 4 1 MIT Plasma Science
More informationGA A22476 DISRUPTION STUDIES IN DIII D
GA A22476 by A.G. KELLMAN, J.W. CUTHBERTSON, T.E. EVANS, D.A. HUMPHREYS, A.W. HYATT, G.L. JAHNS, T. JERNIGAN, C.J. LASNIER, R.L. LEE, J.A. LEUER, S. LUCKHARDT, M.J. SCHAFFER, P.L. TAYLOR, D.G. WHYTE, D.
More informationITER Research Needs. Report by David Campbell Plasma Operation Directorate
ITER Research Needs Report by David Campbell Plasma Operation Directorate Acknowledgements: Members of PO and CHD directorates, together with many experts in the international fusion community The views
More informationScientific Status of ITER
Scientific Status of ITER D J Campbell ITER Organization, Cadarache Acknowledgements: Many colleagues in the ITER IO, ITER Members and ITPA Page 1 Summary of Presentation What are the main changes resulting
More informationTOROIDAL REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO
TOROIDAL REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO C.P.C. Wong, J.C. Wesley, R.D. Stambaugh, E.T. Cheng General Atomics, San Diego, California TSI Research Inc., Solana Beach, California e-mail contact
More informationTaming Plasma-Materials Interface for Steady-State Fusion
Taming Plasma-Materials Interface for Steady-State Fusion by H.Y. Guo, with H. Wang, J.G. Watkins, A.L. Moser, J. Boedo, L. Casali, B. Covele, B. Grierson, M. Groth, D.N. Hill, A.W. Hyatt, L.L. Lao, A.W.
More informationEffectiveness of high-frequency ELM pacing with deuterium and non-fuel pellets in DIII-D
1 EX/10-1 Effectiveness of high-frequency ELM pacing with deuterium and non-fuel pellets in DIII-D A. Bortolon 1, L.R. Baylor 2, R. Maingi 1, D.K. Mansfield 1, A.L. Roquemore 1, R. Lunsford 1, A. Nagy
More informationShattered Pellet Injection as the Primary Disruption Mitigation Technique for ITER
1 EX/9-2 Shattered Pellet Injection as the Primary Disruption Mitigation Technique for ITER D. Shiraki 1, N. Commaux 1, L.R. Baylor 1, N.W. Eidietis 2, E.M. Hollmann 3, V.A. Izzo 3, C.J. Lasnier 4, R.A.
More informationTHE ARIES-I TOKAMAK REACTOR STUDY
THE ARIES-I TOKAMAK REACTOR STUDY Farrokh Najmabadi, Robert W. Conn, and The ARIES Team 16th SOFT London, September 3-7, 1990 ARIES Is a Community-Wide Study U. W. UCLA ANL U. IL. FEDC ORNL RPI ARIES GA
More informationStudies of Impurity Seeding and Divertor Power Handling in Fusion Reactor
1 FIP/P8-11 Studies of Impurity Seeding and Divertor Power Handling in Fusion Reactor K. Hoshino 1, N. Asakura 1, K. Shimizu 2 and S. Tokunaga 1 1 Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212
More informationPlasma Scenarios and Control
Plasma Scenarios and Control R. J. Hawryluk Presented at the SECOND IAEA DEMO PROGRAMME WORKSHOP December 19, 2013 What is the Difference in the Scenario and Control Requirements Between ITER and DEMO?
More informationHigh-density operation with pellets on ASDEX Upgrade - and its impact on the DEMO design
78. DPG-Frühjahrstagung AMOP 17. 21. March 2014, Berlin High-density operation with pellets on ASDEX Upgrade - and its impact on the DEMO design M. Bernert, L. Casali, R. Fischer, O. Kardaun, G. Kocsis,
More informationDevelopment Scenario of Tokamak Reactor for Early Demonstration of Electric Power Generation
Development Scenario of Tokamak Reactor for Early Demonstration of Electric Power Generation US/Japan Workshop on Power Plant Studies and Related Advanced Technologies With EU Participation 24-25 January
More informationC-Mod Advanced Tokamak Program
Advanced Tokamak Program Program Advisory Committee Review February 20, 2003 MIT PSFC Presented by A. Hubbard MIT Plasma Science and Fusion Center, for the team Advanced Tokamak Program Introduction What
More informationDensity Control and Limit(s) in MST
Density Control and Limit(s) in MST M. D. Wyman, B. E. Chapman, S. P. Oliva, S. C. Prager, UW-Madison S. K. Combs, D. T. Fehling, C. R. Foust, ORNL D. L. Brower, W. X. Ding, B. H. Deng UCLA Abstract The
More informationRunaway Electron Transport & Disruption Mitigation Optimization on Alcator C-Mod
Runaway Electron Transport & Disruption Mitigation Optimization on Alcator C-Mod D.G. Whyte 1, R. Granetz 1, V. Izzo 2, M. Reinke 1, G. Olynyk 1 & Alcator C-Mod team 1 MIT Plasma Science & Fusion Center
More informationOverview of ASDEX Upgrade results
Overview of ASDEX Upgrade results Arne Kallenbach on behalf of the ASDEX Upgrade team and the EUROfusion MST1 team* Max-Planck-Institute for Plasma Physics D-85748 Garching *see appendix of H. Meyer et
More informationIntegrated Scenarios: Advanced Regimes
Integrated Scenarios: Advanced Regimes Program Advisory Committee meeting February 4-6, 2009 MIT PSFC Presented by A. Hubbard, for the Advanced Scenarios thrust group Outline Introduction: Scope and niche
More informationFusion Nuclear Science Facility (FNSF) low Q mission range & prerequisites options in associated research program for discussion and feedback
Fusion Nuclear Science Facility (FNSF) low Q mission range & prerequisites options in associated research program for discussion and feedback Normal Plasma Aspect Ratio Embodiment: Fusion Development Facility
More informationPerformance Predictions of RF Heated Plasma in EAST
1 EXC/P2-01 Performance Predictions of RF Heated Plasma in EAST S. Ding 1), B. Wan 1), X. Zhang 1), R. V. Budny 2), Y. Guo 1), D. McCune 2), P. Xu 1), J. Yang 1), J. Qian 1), Y. Shi 1), F. Wang 1), S.
More informationThe role of the density profile location on pedestal stability in ASDEX Upgrade
The role of the density profile location on pedestal stability in ASDEX Upgrade M. G. Dunne, L. Frassinetti, M. Bernert, S. Potzel, F. Reimold 3, E. Viezzer, M. Wischmeier, E. Wolfrum, M. Bernert, M.N.A.
More informationCritical Physics Issues for Tokamak Power Plants
Critical Physics Issues for Tokamak Power Plants D J Campbell 1, F De Marco 2, G Giruzzi 3, G T Hoang 3, L D Horton 4, G Janeschitz 5, J Johner 3, K Lackner 4, D C McDonald 6, D Maisonnier 1, G Pereverzev
More informationStatus and Plans for APEX Task A Plasma/Liquid-Wall Interactions
Status and Plans for APEX Task A Plasma/Liquid-Wall Interactions T.D. * with J. Brooks, T. Evans, A. Hassanein, & M. Rensink* APEX Fall Meeting PPPL Nov. 4, 2002 Work performed under auspices of US DOE;
More informationEX/7-3Ra. Disruption Control on FTU and ASDEX Upgrade with ECRH
1 Disruption Control on FTU and ASDEX Upgrade with ECRH B. Esposito 1), G. Granucci 2), S. Nowak 2), J.R. Martin-Solis 3), L. Gabellieri 1), P. Smeulders 1), M. Maraschek 4), G. Pautasso 4), J. Stober
More informationSCIENCE. Briefing for National Academy of Sciences Board on Physics and Astronomy
OFFICE OF SCIENCE Briefing for National Academy of Sciences Board on Physics and Astronomy Presented by: Dr. Stephen Eckstrand Acting Director Office of Fusion Energy Sciences Office of Science, U.S. Department
More informationTHE PROMISE OF FUSION ENERGY. General Atomics
THE PROMISE OF FUSION ENERGY General Atomics The following slide show is a compilation of slides from many previous similar slide shows that have been produced by different members of the fusion and plasma
More informationCOMPARISON OF STEADY-STATE AND PULSED-PLASMA TOKAMAK POWER PLANTS
COMPARISON OF STEADY-STATE AND PULSED-PLASMA TOKAMAK POWER PLANTS F. Najmabadi, University of California, San Diego and The ARIES Team IEA Workshop on Technological Aspects of Steady State Devices Max-Planck-Institut
More informationTHE UNITED STATES MUST MAINTAIN A WORLD-CLASS DOMESTIC TOKAMAK PROGRAM TO SUPPORT BURNING PLASMA SCIENCE DEVELOPMENT
THE UNITED STATES MUST MAINTAIN A WORLD-CLASS DOMESTIC TOKAMAK PROGRAM TO SUPPORT BURNING PLASMA SCIENCE DEVELOPMENT C.M. Greenfield, 1, 2 D.N. Hill, 1 M.R. Wade 1 1 General Atomics, General Atomics, San
More informationDisruption event characterization and forecasting of global and tearing mode stability for tokamaks
Disruption event characterization and forecasting of global and tearing mode stability for tokamaks J.W. Berkery, S.A. Sabbagh, and J.D. Riquezes Columbia University S.P. Gerhardt and C.E. Myers Princeton
More informationResults from the CDX-U Lithium Wall and NSTX Lithium Pellet Injection and Evaporation Experiments
Results from the CDX-U Lithium Wall and NSTX Lithium Pellet Injection and Evaporation Experiments R. Majeski 1), H. Kugel 1), M.G. Bell 1), R. E. Bell 1), P. Beiersdorfer 5), C. Bush 2), R. Doerner 3),
More informationCOREDIV modelling of JET ILW discharges with different impurity seeding: nitrogen, neon, argon and krypton*
NUKLEONIKA 17;(1): 7 doi: 1./nuka-17-1 ORIGINAL PAPER 17 Irena Ivanova-Stanik et al. This is an open access article distributed under the Creative Commons Attribution -NonCommercial-NoDerivatives. License
More informationParticle fuelling for long pulse with standard gas puff and supersonic pulsed gas injection
EX/P- Particle fuelling for long pulse with standard gas puff and supersonic pulsed gas injection J. Bucalossi, E. Tsitrone, G. Martin, F. Clairet, R. Dejarnac, A. Geraud, P. Ghendrih, C. Gil, C. Grisolia,
More informationPellet fuelling into radiative improved confinement discharges in TEXTOR-94
Pellet fuelling into radiative improved confinement discharges in TEXTOR-9 J. Hobirk a,a.m.messiaen b,k.h.finken a,j.ongena b,m.brix a, R. Jaspers c, H.R. Koslowski a,a.krämer-flecken a,g.mank a,j.rapp
More informationWendelstein 7-X A technology step towards DEMO
A technology step towards DEMO Hans-Stephan Bosch Max-Planck Institute for Plasma Physics Greifswald, Germany 18th Internatinal Toki Conference, December 9 13, 2008, Toki-City, Japan 1-YKA06-Y0001.0 The
More informationX-point Target Divertor Concept
X-point Target Divertor Concept and Alcator DX High Power Density Divertor Test Facility Presented by Brian LaBombard for the Alcator Team Alcator DX Contributed Oral C04.00002 Presented at the 55th Annual
More information5 th INTERNATIONAL CONFERENCE ON THE FRONTIERS OF PLASMA PHYSICS AND TECHNOLOGY April 21, 2011, Singapore
5 th INTERNATIONAL CONFERENCE ON THE FRONTIERS OF PLASMA PHYSICS AND TECHNOLOGY April 21, 2011, Singapore Outline Early history the underpinnings in Basic Studies Tokamak program Aditya and SST-1 - Some
More informationTechnical Specification
IDM UID PVHYAE VERSION CREATED ON / VERSION / STATUS 03 Sep 2014 / 1.0 / Approved EXTERNAL REFERENCE Technical Specification Physics-based transport modelling of main species particle and energy transport
More informationc O N F - y r-elm HEAT FLUX IN THE ITER DIVERTOR
GAmA22899 c O N F - y 60 6 7 r-elm HEAT FLUX IN THE ITER DIVERTOR by AUG 1 OSTI A.W. LEONARD A. HERMANN K. ITAMI J. LINGERTAT A. LOARTE T.H. OSBORNE W. SUTTROP the ITER DIVERTOR MODELING and DATABASE EXPERT
More informationToroidal Reactor Designs as a Function of Aspect Ratio
Toroidal Reactor Designs as a Function of C.P.C. Wong ), J.C. Wesley ), R.D. Stambaugh ), E.T. Cheng ) ) General Atomics, San Diego, California ) TSI Research Inc., Solana Beach, California e-mail contact
More informationThe ITER Research Plan
The ITER Research Plan D.J. Campbell ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance, France Acknowledgements: Many colleagues in the ITER Organization, ITPA and the international
More informationMHD Induced Fast-Ion Redistribution & Loss in AUG
MHD Induced Fast-Ion Redistribution & Loss in AUG Max-Planck Institute for Plasma Physics M. Garcia-Munoz 1 I. G. J. Classen 2, B. Geiger 1, W. W. Heidbrink 3, M. A. Van Zeeland 4, S. Akaslompolo 5, J.
More informationCritical Physics Issues for Tokamak Power Plants
Critical Physics Issues for Tokamak Power Plants D J Campbell 1, F De Marco 2, G Giruzzi 3, G T Hoang 3, L D Horton 4, G Janeschitz 5, J Johner 3, K Lackner 4, D C McDonald 6, D Maisonnier 1, G Pereverzev
More informationStrategic Approach 1 (SA-1): Use present physics and technology basis for DEMO.
Strategic Approach 1 (SA-1): Use present physics and technology basis for DEMO. Steve Zinkle, David Newman, Wayne Solomon, Francesca Turco, SA-1 co-chairs 1. Brief description of the strategic approach
More informationTokamak KTM Complex for Material Investigation
Tokamak KTM Complex for Material Investigation I.L.Tazhibayeva 1), E.A. Azizov 2), V.A. Krylov 3), V.P. Shestakov 4), O.S. Pivovarov 1), V.L. Raspopin 5) 1) National Nuclear Center, Kazakhstan 2) Troitsk
More informationDevelopment and Application of System Analysis Program for Parameters Optimization and Economic Assessment of Fusion Reactor (SYSCODE)
Development and Application of System Analysis Program for Parameters Optimization and Economic Assessment of Fusion Reactor (SYSCODE) Presented By Dehong Chen Contributed by FDS Team Key Laboratory of
More informationStatus Report and Documentation of DCLL Design
Status Report and Documentation of DCLL Design He primary and secondary loops footprint at TCWS DCLL design evolution DCLL, DEMO inboard routing assessment Documentation of DCLL design Clement Wong, Dick
More informationIntegrated Scenarios: Advanced Regimes
Integrated Scenarios: Advanced Regimes Program Advisory Committee meeting January 27-29, 2010 MIT PSFC Presented by A. Hubbard, for the Advanced Scenarios thrust group v7 1/28/10 Outline Introduction:
More informationInvestigations on the ELM cycle by local 3D perturbation experiments
Final Version (February 2, 26) Investigations on the ELM cycle by local 3D perturbation experiments P.T. Lang, K. Gal o, J. Hobirk, S. Kalvin o,g.kocsis o, V. Mertens, J. Neuhauser, M. Maraschek, W. Suttrop,
More informationReport on the US-Japan Workshop- Plasma Fueling and Active Particle Control
II UCRL-ID-138066 II I I ; r. Report on the US-Japan Workshop- Plasma Fueling and Active Particle Control Keith I. Thomassen March 1, 2000 II II II U.S. Department of Energy Lawrence Livermore National
More informationDEVELOPMENT OF PHYSICS AND ENGNEERING DESIGNS FOR JAPAN S DEMO CONCEPT
Y. SAKAMOTO et al. DEVELOPMENT OF PHYSICS AND ENGNEERING DESIGNS FOR JAPAN S DEMO CONCEPT Y. SAKAMOTO National Institutes for Quantum and Radiological Science and Technology, Fusion Energy Research Development
More informationGA A26417 MECHANICAL DESIGN OF THE POSITIONING SYSTEM FOR AN OFF-AXIS NEUTRAL BEAM
GA A26417 MECHANICAL DESIGN OF THE POSITIONING SYSTEM FOR AN OFF-AXIS NEUTRAL BEAM by P.M. ANDERSON and R.-M. HONG JUNE 2009 DISCLAIMER This report was prepared as an account of work sponsored by an agency
More informationOctober 17-22, MHD dynamo EMF of helical core. by P. Piovesan. Presented at the 26 th IAEA Fusion Energy Conference, Kyoto, Japan
Role of MHD Dynamo in the Formation of 3D Equilibria in Fusion Plasmas by P. Piovesan MHD dynamo EMF of helical core ExB flow DIII-D Presented at the 26 th IAEA Fusion Energy Conference, Kyoto, Japan October
More informationNeutral Beam Heating on the TCV Tokamak
EUROFUSION WPMST1-CP(16) 16586 B Duval et al. Neutral Beam Heating on the TCV Tokamak Preprint of Paper to be submitted for publication in Proceedings of 26th IAEA Fusion Energy Conference This work has
More informationAT Task Force Summary. Amanda Hubbard C-Mod Ideas Forum 2005 Dec 2-6, 2004
AT Task Force Summary Amanda Hubbard C-Mod Ideas Forum 2005 Dec 2-6, 2004 Main goals of the AT physics program (from 5-yr plan 2003) 1. Demonstrate and model current profile control using LH and ICRF waves,
More informationDEMO Concept Development and Assessment of Relevant Technologies
1 FIP/3-4Rb DEMO Concept Development and Assessment of Relevant Technologies Y. Sakamoto, K. Tobita, H. Utoh, N. Asakura, Y. Someya, K. Hoshino, M. Nakamura, S. Tokunaga and the DEMO Design Team Japan
More informationPellet Fueling, ELM pacing, and Disruption Mitigation Technology Development for ITER
1 IT/P6-19 Pellet Fueling, ELM pacing, and Disruption Mitigation Technology Development for ITER L.R. Baylor 1, S.K. Combs 1, C.R. Foust 1, T.C. Jernigan 1, S. J. Meitner 1, P.B. Parks 2, J.B. Caughman
More informationNumerical analyses of baseline JT-60SA design concepts with the COREDIV code
1 TH/P6-24 Numerical analyses of baseline JT-60SA design concepts with the COREDIV code R. Zagórski 1, K.Gałązka 1, I. Ivanova-Stanik 1, W.Stępniewski 1, L.Garzotti 2, G.Giruzzi 3, R.Neu 4 and M.Romanelli
More informationTHE ARIES TOKAMAK REACTOR STUDIES
THE ARIES TOKAMAK REACTOR STUDIES Farrokh Najmabadi for The ARIES Team Fusion Power Associates Symposium Pleasanton, CA, April 9-10, 1992 ARIES Is a Community-Wide Study ANL UCLA GA MIT LANL PPPL ARIES
More informationThe role of RF in the optimized shear scenario on JET
The role of RF in the optimized shear scenario on JET F. X. Söldner, B. Alper, Yu. F. Baranov, A. Bickley, A. Bondeson et al. Citation: AIP Conf. Proc. 485, 288 (1999); doi: 1.163/1.59749 View online:
More informationThe FTU facilities. During 2006, the machine again operated at the high level of 91% of successful pulses.
The FTU facilities FTU Machine Summary of the machine operation During 2006, the machine again operated at the high level of 91% of successful pulses. The experimental activity started at the end of March
More information(Draft) ALCATOR C-MOD FY06-07 WORK PROPOSAL
(Draft) ALCATOR C-MOD FY06-07 WORK PROPOSAL March 2005 Submitted to: Office of Fusion Energy Sciences Office of Energy Research U.S. Department of Energy Germantown, MD 20874 Plasma Science and Fusion
More information(Draft) FY04-FY05 WORK PROPOSAL March 2003
(Draft) FY04-FY05 WORK PROPOSAL March 2003 Submitted to: Office of Fusion Energy Sciences Office of Energy Research U.S. Department of Energy Germantown, MD 20874 Alcator Project Principal Investigators:
More informationELM suppression in Lithium-conditioned NSTX
ELM suppression in Lithium-conditioned NSTX Debabrata Banerjee 1, Ping Zhu 1,2, and Rajesh Maingi 3 University of Science and Technology of China 1 University of Wisconsin-Madison 2 Princeton Plasma Physics
More informationOVERVIEW OF THE ARIES AND PULSAR STUDIES
OVERVIEW OF THE ARIES AND PULSAR STUDIES F. Najmabadi, R. W. Conn, University of California, San Diego and The ARIES Team ISFNT-3 University of California, Los Angeles June 27 July 1, 1994 ARIES Is a Community-Wide
More informationDivertor and Edge Physics
Divertor and Edge Physics Goals Recent results Near-term plans Five-year outlook Presented by B. LaBombard Divertor and Edge Physics Research Goals! Advance physics understanding in key divertor and edge
More informationCompeted ITER Task Agreements (ITAs, for information and expression of interest)
Competed ITER Task Agreements (ITAs, for information and expression of interest) ONGOING CALLS Ref F4E-CITA-002: "Evaluation of edge MHD stability and uncontrolled ELM energy losses for ITER H-mode plasmas
More informationResearch Thrust to Address Major Measurement Gaps
Research Thrust to Address Major Measurement Gaps RENEW Workshop Presentation Theme: Plasma Material Interface Subpanel on Internal Components Presented by Tony Peebles, UCLA Physics & Astronomy Department:
More informationOperation of DIII-D National Fusion Facility and Related Research Cooperative Agreement DE-FC02-04ER54698 (GA Project 30200)
May 10, 2010 Dr. Mark Foster U. S. Department of Energy Office of Science General Atomics Site/Bldg. 7 Rm. 119 3550 General Atomics Ct. San Diego, CA 92121 Reference: Operation of DIII-D National Fusion
More informationReflections on Fusion Chamber Technology and SiC/SiC Applications Mohamed Abdou UCLA
Reflections on Fusion Chamber Technology and SiC/SiC Applications Mohamed Abdou UCLA Presented at CREST Conference, Kyoto, Japan, May 21, 2002 The Region Immediately Surrounding the Plasma Divertor / First
More informationSummary of Task B Activities*
Summary of Task B Activities* R. Kaita and R. Woolley Princeton Plasma Physics Laboratory APEX Electronic Meeting 20 13 and 15 August 2002 *with contributions from M. Ulrickson, B. Nelson, A. Hassanein,
More informationVerification of NIMROD and ELITE MHD codes for the Developement of a Model for the Width of ELM Crashes
Lehigh University, Bethlehem, PA pankin@lehigh.edu Verification of NIMROD and ELITE MHD codes for the Developement of a Model for the Width of ELM Crashes A. Y. PANKIN1, G. BATEMAN1, P. B. SNYDER2, D.
More informationExperimental and Design Activity on Liquid Lithium Divertor
Experimental and Design Activity on Liquid Lithium Divertor V.A. Evtikhin 1), I.E. Lyublinski 1), A.V. Vertkov 1), A.N. Chumanov 1), N.M. Afanasiev 1), V.N. Shpoliansky 1), B.I. Khripunov 2), V.B. Petrov
More information