C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 1 Steady State Operation & Energetic Particles Advanced Scenario need the same development path.

Slides:



Advertisements
Similar presentations
1/15 D. C. McDonald et al, Particle and Energy Transport in Dedicated  *,  and  * Scans in JET ELMy H-modes, IAEA - 20th Fusion Energy Conference, Vilamoura,
Advertisements

Stability, Transport, and Conrol for the discussion Y. Miura IEA/LT Workshop (W59) combined with DOE/JAERI Technical Planning of Tokamak Experiments (FP1-2)
I. Opening I-1. Welcome address U.Stroth I-2. Logistics M.Ramisch I-3. Opening remarks H.Yamada II. Definition of the goal of CWGM5 II-1. Brief review.
George Sips ITPA, active control, 14 July Real-time Control ( and development of control systems ) at ASDEX Upgrade George Sips Max-Planck-Institut.
1 G.T. Hoang, 20th IAEA Fusion Energy Conference Euratom Turbulent Particle Transport in Tore Supra G.T. Hoang, J.F. Artaud, C. Bourdelle, X. Garbet and.
Association Euratom-FOM Trilateral Euregio Cluster 1 M.R. de Baar, Workshop Control for Nuclear Fusion, the Netherlands, In the control room:
Emmanuel JoffrinXXth Fusion Energy Conference, November The « hybrid » scenario in JET: towards its validation for ITER E. Joffrin, A. C. C. Sips,
IAEA - FEC2004 // Vilamoura // // EX/4-5 // A. Staebler – 1 – A. Staebler, A.C.C Sips, M. Brambilla, R. Bilato, R. Dux, O. Gruber, J. Hobirk,
Critical Physics Issues for DEMO Max-Planck-Institut für Plasmaphysik L.D. Horton with thanks to the speakers at the recent European Fusion Physics Workshop.
Physics of fusion power Lecture 8 : The tokamak continued.
Steady State High  N Discharges and Real-Time Control of Current Profile in JT-60U T. Suzuki 1), A. Isayama 1), Y. Sakamoto 1), S. Ide 1), T. Fujita 1),
IOS-5.2 Maintaining ICRH Coupling in expected ITER regime Spokes person: M. Goniche M.-L. Mayoral (JET), R. Pinsker (DIII-D), L. Colas (TS), V. Bobkov.
D. Borba 1 21 st IAEA Fusion Energy Conference, Chengdu China 21 st October 2006 Excitation of Alfvén eigenmodes with sub-Alfvénic neutral beam ions in.
Prof. F.Troyon“JET: A major scientific contribution...”25th JET Anniversary 20 May 2004 JET: A major scientific contribution to the conception and design.
M.E. Fenstermacher - Summary of Progress and Outlook for Work Plan in PEP ITPA WG on RMP ELM Control 4/23/09 11:15 PM 1 PEP ITPA Working Group on RMP ELM.
ITPA - IOS st Oct Kyoto E. Joffrin JET programme with the ILW in and relations with the IOS Joint experiments.
Divertor/SOL contribution IEA/ITPA meeting Naka Nov. 23, 2003 Status and proposals of IEA-LT/ITPA collaboration Multi-machine Experiments Presented by.
Analysis and Simulations of the ITER Hybrid Scenario C. Kessel, R. Budny, K. Indireshkumar Princeton Plasma Physics Laboratory, USA ITPA Topical Group.
H-mode characteristics close to L-H threshold power ITPA T&C and Pedestal meeting, October 09, Princeton Yves Martin 1, M.Greenwald, A.Hubbard, J.Hughes,
ITPA-Transport TG Particle & impurity workgroup Discussion, future plans Milano,
S.A. Sabbagh for NSTX Macrostability TSG Macrostability TSG Suggested FY-12 Milestones – Address key ReNeW issues for ST development 1) Assess sustained.
9th ITPA Confinement Database and Modelling Topical Physics Group meeting in St. Petersburg 1/5 NF paper on H-mode confinement DB3 Darren McDonald.
AES, ANL, Boeing, Columbia U., CTD, GA, GIT, LLNL, INEEL, MIT, ORNL, PPPL, SNL, SRS, UCLA, UCSD, UIIC, UWisc FIRE Collaboration FIRE.
Integrated Modeling and Simulations of ITER Burning Plasma Scenarios C. E. Kessel, R. V. Budny, K. Indireshkumar, D. Meade Princeton Plasma Physics Laboratory.
Status of the ASDEX Upgrade Tokamak Programme Hartmut Zohm MPI für Plasmaphysik, EURATOM Association Joint Executive Committee session of IEA-IAs on Pol.
V. A. Soukhanovskii NSTX Team XP Review 31 January 2006 Princeton, NJ Supported by Office of Science Divertor heat flux reduction and detachment in lower.
AES, ANL, Boeing, Columbia U., CTD, GA, GIT, LLNL, INEEL, MIT, ORNL, PPPL, SNL, SRS, UCLA, UCSD, UIIC, UWisc FIRE Collaboration FIRE.
L-H threshold database: Status and Plans J.W. Hughes, J. Stillerman, MIT PSFC Y. Martin, CRPP-EPFL P. Gohil, GA D. McDonald, JET-EFDA Meeting of the ITPA.
NSTX-U NSTX-U PAC-31 Response to Questions – Day 1 Summary of Answers Q: Maximum pulse length at 1MA, 0.75T, 1 st year parameters? –A1: Full 5 seconds.
High  p experiments in JET and access to Type II/grassy ELMs G Saibene and JET TF S1 and TF S2 contributors Special thanks to to Drs Y Kamada and N Oyama.
Yves Martin Centre de Recherches en Physique des Plasmas Association Euratom - Confédération Suisse Ecole Polytechnique Fédérale de Lausanne (EPFL) CH.
OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia O u t l i n e Goal of the work The DINA code capabilities Formulation of the.
PF1A upgrade physics review Presented by D. A. Gates With input from J.E. Menard and C.E. Kessel 10/27/04.
1ITPA meeting IOS, Oct 2011Arne Kallenbach IOS-1.2 Study seeding effects on ITER demo discharges (Oct 2011) - closely related to IOS-1.1, development of.
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
1 Instabilities in the Long Pulse Discharges on the HT-7 X.Gao and HT-7 Team Institute of Plasma Physics, Chinese Academy of Sciences, P.O.Box 1126, Hefei,
F P Orsitto ENEA Frascati 12th ITPA Princeton march 071 Report on the meeting of ITPA TG Steady-State Operations and ITPA TG Transport proposal Francesco.
OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia O u t l i n e Goal of the work The DINA code capabilities Formulation of the.
FOM - Institute for Plasma Physics Rijnhuizen Association Euratom-FOM Diagnostics and Control for Burning Plasmas Discussion All of you.
E. Doyle (Chair), V. Mukhovatov (Co-chair) for the ITPA Transport Physics Group 2nd IEA Large Tokamak Workshop on Implementation of the ITPA Coordinated.
Integrated Operation Scenarios ITPA Remaining duties ITPA CC meeting & IEA/ITPA JE planning meeting –12 – 14 (15) December 2011, Cadarache –Ide, Sips and.
EJD IAEA H-mode WS,, September 28, Overview Introduction — steady-state performance requirements -Global DIII-D and NSTX progress Plasma control.
ITPA Topical Group on MHD, Control, and Disruptions Summary of 5th meeting, Nov. 8-10, 2004 Presented by Ted Strait Workshop on MHD Mode Control Princeton,
ITER STEADY-STATE OPERATIONAL SCENARIOS A.R. Polevoi for ITER IT and HT contributors ITER-SS 1.
AES, ANL, Boeing, Columbia U., CTD, GA, GIT, LLNL, INEEL, MIT, ORNL, PPPL, SNL, SRS, UCLA, UCSD, UIIC, UWisc NSO Collaboration Implications.
JT-60U -1- Access to High  p (advanced inductive) and Reversed Shear (steady state) plasmas in JT-60U S. Ide for the JT-60 Team Japan Atomic Energy Agency.
RFX workshop / /Valentin Igochine Page 1 Control of MHD instabilities. Similarities and differences between tokamak and RFP V. Igochine, T. Bolzonella,
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
TPB Structure St.. Petersburg NEXT STEPS IN PROCESS Approach identified participants to ensure they are willing/able to participate Section coordinators.
DISCUSSION OF ISSUES, OPPORTUNITIES AND CONCLUSIONS FOR ROTATION AND MOMENTUM TRANSPORT SESSIONS 10th ITPA Transport Physics and CDBM TG Meetings Princeton.
Improved performance in long-pulse ELMy H-mode plasmas with internal transport barrier in JT-60U N. Oyama, A. Isayama, T. Suzuki, Y. Koide, H. Takenaga,
TRANSP for core particle transport studies M. Maslov.
SUMMARY OF 4th IPTA TRANSPORT AND ITB PHYSICS TG MEETING St. Petersburg, Russia, April 8-11, 2003 Presented by E.J. Doyle for the TG Note: this summary.
Steady State Discharge Modeling for KSTAR C. Kessel Princeton Plasma Physics Laboratory US-Korea Workshop - KSTAR Collaborations, 5/19-20/2004.
Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.
20th IAEA Fusion Energy Conference, 2004 Naka Fusion Research Establishment, Japan Atomic Energy Research Institute Stationary high confinement plasmas.
1 SIMULATION OF ANOMALOUS PINCH EFFECT ON IMPURITY ACCUMULATION IN ITER.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
Advanced Tokamak Modeling for FIRE C. Kessel, PPPL NSO/PAC Meeting, University of Wisconsin, July 10-11, 2001.
FY WEP TSG Goals & WEP-Relevant Diagnostic Upgrades NSTX Supported by WEP TSG Meeting September 14,
Status of NSTX/DIII-D/MAST aspect ratio core confinement comparison studies M. Peng, for E.J. Synakowski For the ITPA Transport Physics Working Group Kyota,
Yves Martin Centre de Recherches en Physique des Plasmas Association Euratom - Confédération Suisse Ecole Polytechnique Fédérale de Lausanne (EPFL) CH.
Off-axis Current Drive and Current Profile Control in JT-60U T. Suzuki, S. Ide, T. Fujita, T. Oikawa, M. Ishikawa, G. Matsunaga, M. Takechi, M. Seki, O.
6 th ITPA MHD Topical Group Meeting combined with W60 IEA Workshop on Burning Plasmas Summary Session II MHD Stability and Fast Particle Confinement chaired.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
1 J. Garcia ITPA-IOS meeting Kyoto October 2011 Association Euratom-CEA Free boundary simulations of the ITER hybrid and steady-state scenarios J.Garcia.
To ‘B’ or not to ‘B’ That is the question
ITERに係わる原子分子過程 Atomic and Molecular Processes in ITER SHIMADA, Michiya ITER International Team Annual Meeting of Japan Society of Plasma Science and Nuclear.
Joint Experiment IOS-4.1 Aims:
Density Peaking in JET (NBI fueling dominant) and DIII-D (transport dominant) Originates from Different Sources at Low υ* For the first time electron particle.
Presentation transcript:

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 1 Steady State Operation & Energetic Particles Advanced Scenario need the same development path as the reference ITER H-mode scenario oMulti-machine experiments essential to develop common vocabulary and experience oProgressive build-up of integration issues Scenarios seems to depend upon current profile: oHybrid Scenarios oSteady-State scenarios At this stage proposals are generic since related to scenario operation development: odetailed proposals will be made by ROs following approval Specific joint experiments on Energetic Particles not being made: oJoint data analysis is highly recommended

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 2 IEA-LT/ ITPA Collaboration : Hybrid Scenario Definition: oThe objective of the ITER Hybrid scenario is the maximum fluence/year(pulse). High priority in 2003 omap the existence domain for each machine oidentify across the domain the mechanism by which the current is prevented from peaking (fishbones, tearing mode, etc.). Variations of performance (e.g.,  ) with q 95 density and shape at fixed field and shape are of high interest. ROs: E.Joffrin, G.Sips, M.Wade, A.Isayama (S.Wolfe)

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 3 Proposals for International Collaboration in 2004 Hybrid scenario oComplete mapping existence domain  AUG may need more time on q 95 scan.Older ASDEX Upgrade results already span a range of densities  DIIID needs more time on density scan; needs a little time for q 95 scan  JET established scenario at q 95 = 4; mapping not started (Nov but not in 2004).  JT60 established scenario at q 95 = 3.6; mapping not started (starting in Dec. 2003)  C-MOD: A proposal has been made to use new hardware (LHCD in particular) to access hybrid regime

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 4 Hybrid scenario (2) Compare effects of tearing modes, fishbones, and sawteeth in this regime among machines ocurrent profile broadening, oconfinement reduction, ofast ion transport with fishbones, ofast ion effects on sawteeth)  This may not require additional run time immediately, but rather a coordinated analysis effort of the domain mapping discharges, which may lead to dedicated experiments. Investigations of Te/Ti effect on confinement in hybrid scenarios oAll machines have some capability to replace neutral beam power with ICRF or EC, which will heat the electrons.

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 5 IEA-LT/ ITPA Collaboration : Steady State Scenario Definition: The objective of the ITER Steady state scenario is 100% non-inductive operation at Q>5. Joint experiments to probe the performance limits are proposed with the following specifications on the q profile: q 95 =4-5, q min = , q (0) -q min 3 and f BS >0.5 and are at present the most promising for ITER. Experiments with other q profiles have realized fully non- inductive sustainment. Candidate profiles for steady state should test consistency with Q>5 in burning plasma conditions.

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 6 Steady State Operation: Priorities in 2003 High priority for the four large divertor machines oexplore performance limits with the recommended q profile and compare the results. ROs: X.Litaudon, J.Hobirk, T.Luce, S.Ide, (A.Hubbard)

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 7 Proposals for International Collaboration in 2004 Steady-state scenario oDocument performance boundaries for the agreed current profile Performance includes the assessment of the potential for each machine to achieve fully non-inductive operation with that q profile  AUG: scenario has not been established  DIIID beta limit studies with variation in shape and pressure profiles has been done; –experiments with fully non-inductive operation still require time  JET: scenario to study performance limits (with present heating&CD capability) needs to be developed (unlikely in Dec.2003, not in 2004)  JT-60U: scenario was established in the past; to be re- established with modern diagnostics and heating systems (starting Dec. 2003, priorities being decided)

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 8 Steady State Scenario (ctd) The key to pushing forward steady-state scenario is to have a demonstration of performance levels in JET or JT-60U which can be reasonably projected to burning plasmas. oDevelopment of such a scenario is consistent with the JT- 60U goals for 2004 oOther scenarios (different q profile, very hollow in particular) established on one machine to be tested in another machine (possible proposal from JT-60U) Increase significantly collaboration between groups owill greatly enhance the probability of success

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 9 Impressive agreement between AUG,DIIID and JET Hybrid Scenario established on JET omatching elongation, aspect ratio, triangularity, q-profile and  *,all AUG features are recovered:  H ITER89P x  N ~5.9 at q 95 ~3.9  N up to 2.8 oHybrid regime achieved at lower  * (2.5T/2.1MA) but not at the lowest  * value (3.4T/2.8MA). At low q 95 ~ : sawteeth remain, lower beta limits  N =2.5 in AUG, 2.7 in DIIID For q 95 =3.8-4: sawteeth free, hybrid regime established only with dominant off axis NBI in AUG At q 95 >4:  N up to 3.2 in DIIID and AUG (limited by2/1 NTMs) The required values of  N H/q 95 2 to operate ITER at Q=10 have been achieved in DIIID, AUG and marginally in JET

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 10 Joint Hybrid Experiments AUG/JET similarity scenarios. JET hybrid established DIIID Extrapolation from # to ITER shows high fluence possible

C Gormezano, S Ide ITPA SSO&EP IEA-LT/ ITPA Collaboration 11 Performance limits only done in DIIID Difficulties in JET (pressure of time, other priorities such as active control on very long pulses), JT-60 has not yet resumed operation, regime difficult to achieve in AUG (in addition problems with MSE)  N above no-wall limit. Not a large change with shaping, similar  N /li values No-wall  N limit and max. exp.  N decrease as q min increases. Very important result to be checked on other machines