ContributorsEuratom Associations L. Carraro, M. Mattioli, M.E. Puiatti, P. Scarin, B. Zaniol Consorzio RFX, Padova, Italy P.DuMortier, A. Messiaen, J OngenaEcole.

Slides:



Advertisements
Similar presentations
Glenn Bateman Lehigh University Physics Department
Advertisements

ASIPP HT-7 belt limiter Houyang Guo, Sizhen Zhu and Jiangang Li Investigation of EAST Divertor Asymmetry in Plasma Detachment & Target Power Loading Using.
H. Weisen 1 21st IAEA FEC, Chengdu 2006 Peaked Density Profiles in Low Collisionality H-modes in JET, ASDEX Upgrade and TCV H. Weisen, C. Angioni, M. Maslov,
9th TTF Spain September 11, 2002 B. J. Peterson, NIFS, Japan page 1 Radiative Collapse and Density Limit in the Large Helical Device.
RFP Workshop Stockholm 9-11 / 10 / 2008 High Density Limit in RFP’s M Valisa and the RFX-mod team.
RFP Workshop, Stockholm 9-11 /10/ 2008 Numerical studies of particle transport mechanisms in RFX-mod low chaos regimes M.Gobbin, L.Marrelli, L.Carraro,
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.
R Sartori - page 1 20 th IAEA Conference – Vilamoura Scaling Studies of ELMy H-modes global and pedestal confinement at high triangularity in JET R Sartori.
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,
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
RFX-mod Workshop – Padova, January Experimental QSH confinement and transport Fulvio Auriemma on behalf of RFX-mod team Consorzio RFX, Euratom-ENEA.
E1/E2 Meeting, 7 April Achievements and open issues in impurity profile control at JET. M. Valisa and Angioni Carraro Coffey Lauro-Taroni Predebon.
10th ITPA TP Meeting - 24 April A. Scarabosio 1 Spontaneous stationary toroidal rotation in the TCV tokamak A. Scarabosio, A. Bortolon, B. P. Duval,
Valisa et al C-mod Ideas Forum, 8 April Electron heating and Ni / Mo Pump Out L Carraro, I Predebon, ME Puiatti, M Valisa ( Consorzio RFX Padova)
TOTAL Simulation of ITER Plasmas Kozo YAMAZAKI Nagoya Univ., Chikusa-ku, Nagoya , Japan 1.
PIC simulations of the propagation of type-1 ELM-produced energetic particles on the SOL of JET D. Tskhakaya 1, *, A. Loarte 2, S. Kuhn 1, and W. Fundamenski.
ITPA-Transport TG Particle & impurity workgroup Discussion, future plans Milano,
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
Excitation of ion temperature gradient and trapped electron modes in HL-2A tokamak The 3 th Annual Workshop on Fusion Simulation and Theory, Hefei, March.
The study of MARFE during long pulse discharges in the HT-7 tokamak W.Gao, X.Gao, M.Asif, Z.W.Wu, B.L.Ling, and J.G.Li Institute of Plasma Physics, Chinese.
THE WEST PROJECT AND RELATED ACTIVITIES AT CEA-IRFM 24/09/2012ADAS WORKSHOP | PAGE 1 CEA | 10 AVRIL 2012 R. Guirlet, J. Bucalossi, M. Firdaouss, Y. Marandet,
Rotation effects in MGI rapid shutdown simulations V.A. Izzo, P.B. Parks, D. Shiraki, N. Eidietis, E. Hollmann, N. Commaux TSD Workshop 2015 Princeton,
October Milano Core-Pedestal Energy Confinement. Empirical Scaling Laws and "stiff" profiles. A. Jacchia 1, F. De Luca 2 1 Consiglio Nazionale.
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.
ITER Standard H-mode, Hybrid and Steady State WDB Submissions R. Budny, C. Kessel PPPL ITPA Modeling Topical Working Group Session on ITER Simulations.
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.
Carine Giroud 1 ITPA Naka Impurity transport at JET On-going analysis from recent campaign C. Giroud, C. Angioni, L. Carraro, P. Belo, I. Coffey,
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.
1 Max-Planck-Institut für Plasmaphysik 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila ELM resolved measurements of W sputtering MPI für Plasmaphysik.
Plasma-wall interactions during high density operation in LHD
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.
Transport in three-dimensional magnetic field: examples from JT-60U and LHD Katsumi Ida and LHD experiment group and JT-60 group 14th IEA-RFP Workshop.
ASIPP HT-7 The effect of alleviating the heat load of the first wall by impurity injection The effect of alleviating the heat load of the first wall by.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.
ITER STEADY-STATE OPERATIONAL SCENARIOS A.R. Polevoi for ITER IT and HT contributors ITER-SS 1.
B WEYSSOW 2009 Coordinated research activities under European Fusion Development Agreement (addressing fuelling) Boris Weyssow EFDA-CSU Garching ITPA 2009.
Angelo A. Tuccillo EX/ th IAEA Fusion Energy Conference, Vilamoura, 1-6 November 2004 Development on JET of Advanced Tokamak Operations for ITER.
RFX workshop / /Valentin Igochine Page 1 Control of MHD instabilities. Similarities and differences between tokamak and RFP V. Igochine, T. Bolzonella,
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,
ISM Working Group 1 ITPA meeting 24 th March 2010 Modelling of JET, Tore Supra and Asdex Upgrade current ramp-up experiments F. Imbeaux, F. Köchl, D. Hogeweij,
RFX-mod Workshop, Padova 20-22/01/ 2009 Transport in the Helical Core of the RFP M.Gobbin, G.Spizzo, L.Marrelli, L.Carraro, R.Lorenzini, D.Terranova and.
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.
9 th EU-US Transport Task Force Workshop, Córdoba, Spain, 9-12 September 2002Luca Garzotti1 Particle transport and density profile behaviour on JET L.
M. Greenwald, et al., APS-DPP 2006 Density Peaking At Low Collisionality on Alcator C-Mod APS-DPP Meeting Philadelphia, 10/31/2006 M. Greenwald, D. Ernst,
1 SIMULATION OF ANOMALOUS PINCH EFFECT ON IMPURITY ACCUMULATION IN ITER.
Role of thermal instabilities and anomalous transport in the density limit M.Z.Tokar, F.A.Kelly, Y.Liang, X.Loozen Institut für Plasmaphysik, Forschungszentrum.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
Carine Giroud 1 21st IAEA Fusion Energy, Chengdu Carine Giroud 1 IAEA, Chengdu Progress in understanding impurity transport at JET.
Enhanced D  H-mode on Alcator C-Mod presented by J A Snipes with major contributions from M Greenwald, A E Hubbard, D Mossessian, and the Alcator C-Mod.
ZHENG Guo-yao, FENG Kai-ming, SHENG Guang-zhao 1) Southwestern Institute of Physics, Chengdu Simulation of plasma parameters for HCSB-DEMO by 1.5D plasma.
Fast response of the divertor plasma and PWI at ELMs in JT-60U 1. Temporal evolutions of electron temperature, density and carbon flux at ELMs (outer divertor)
RFX Meeting G. Mazzitelli Padova 21/01/09 Lithization on FTU: tools and results G. Mazzitelli a Many thanks to:M.L. Apicella a, V. Pericoli Ridolfini a,
Localised Neutron Emission at the edge of high density JET Trace Tritium - ELMy H-mode plasmas A.Murari 6 on the behalf of G. Bonheure 1, S. Popovichev.
M Valisa 1 25 th IAEA FEC, St Petersburg Oct 2014 Heavy Impurity Transport in the Core of JET Plasmas M Valisa C Angioni 2, R. Bilato 2, F J Casson.
Decrease of transport coefficients in the plasma core after off-axis ECRH switch-off K.A.Razumova and T-10 team.
9-12 Sept. 2002E. BARBAT0-ENEA, TTF, Cordoba1 Electron Internal Transport barriers by LHCD and ECRH in FTU-high density plasmas E. Barbato Associazione.
SAWTOOTH AND M=1 MODE BEHAVIOUR IN FTU PELLET ENHANCED DISCHARGES
Impurity transport characterisation JET operational scenarios
Features of Divertor Plasmas in W7-AS
Similarities and differences in SOL physics
L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European.
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.
Investigation of triggering mechanisms for internal transport barriers in Alcator C-Mod K. Zhurovich C. Fiore, D. Ernst, P. Bonoli, M. Greenwald, A. Hubbard,
T. Morisaki1,3 and the LHD Experiment Group
T. Morisaki1,3 and the LHD Experiment Group
H. Nakano1,3, S. Murakami5, K. Ida1,3, M. Yoshinuma1,3, S. Ohdachi1,3,
EX/6-1 Heavy Impurity Transport in the Core of JET Plasmas
C.Mazzotta Peaked Density Profiles due to Neon Injection on FTU
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

ContributorsEuratom Associations L. Carraro, M. Mattioli, M.E. Puiatti, P. Scarin, B. Zaniol Consorzio RFX, Padova, Italy P.DuMortier, A. Messiaen, J OngenaEcole Royal Militaire, Brussels, Belgium R.Dux, IPP-Euratom Assoziation, Garching Germany M.F.F NaveCentro de Fusão Nuclear, 1096Lisbon, Portugal J.Rapp, B. UnterbergIPF Jülich GmbH, Jülich, Germany L. Gabellieri,D. Frigione, L. Pieroni ENEA, Frascati, Italy Impurity Transport in High Density Plasmas in JET and FTU 9th EU-US Transport Task Force Workshop Cordoba, Spain - Sept / 2002 Presented by M. Valisa Task Forces S1 and T/impurity transport

Content High density regimes (relative to the Greenwald limit) of good confinement quality can be obtained in several ways Here we concentrate the impurity transport analysis on the high density Radiatively Improved Modes experiments carried out in JET (ELMy H mode) and FTU (Ohmic) JET: injection of ICRH on top of NBI heating changes transport in the core and avoids impurity accumulation in Ar seeded quasi stationary D discharges with high density (n e /n G ~ 0.9), good confinement (H 98 ~ 1) and high power radiated fraction (> 50 %). FTU : Ne seeding of D plasmas avoids saturation of confinement with density and the radiation belt at the edge reduces significantly the metal influx, with no major modification of the impurity transport.

Increasing interest in High Density regimes - around Greenwald limit - because reactor relevant. In this context impurities are an important issue: - radiative effectiveness /core power dissipation [ Prad ≈ n e n imp L(T e..) ] - risk of accumulation in the core when confinement improves - beneficial effects in accessing high density regimes w/o confinement degradation (e.g. RI-modes ) - beneficial effects as a heat exhaust channel Same impurity transport model used to analyze the two different experiments Motivation

Background - 1: Radiatively Improved mode Integrated scenario combining - high confinement ( increasing with density) - high density - good heat exhaust capability (edge radiating belt) - acceptable Zeff. Obtained in Textor-94 ( ISX results of 1984) by seeding the plasma with impurities (Ne, Ar, Si) and then reproduced in several experiments ( Asdex-UG, TFTR, D III-D, JT-60, FTU, JET). For an overview see J. Ongena et al., Physics of Plasmas 8 (2001) 2188

Background 2: Impurity accumulation Accumulation of impurities depends on the combination of various processes Transport Processes Anomalous transport - Typically flattens profiles Neoclassical transport Edge transport/ ELM’s/ screening PWI Impurity production mechanisms Impurity net influx

The analysis method : 1 D impurity transport model (M.Mattioli’s) Ionisation, recombination and radial transport of the ions of charge Z: Radiative, dielectronic, charge-exchange recombination Impurity influx is given as boundary condition, its time evolution is determined by tracking the brightness of peripheral lines. The transport coefficients D and v, radius and time dependent, are chosen in such a way as to obtain the best ‘global’ simulation of the available experimental data: Emission line spectra SXR Bolometry.

Radiatively improved modes in JET Elmy H mode Radiatively improved modes obtained in Jet in various configurations, heating schemes and puffing rates. Example : Shot Low triangularity (  ~ 0.22) X-point on septum. Ar Puffing. ITER ref. Scenario : H 98 =1,  N =1.8, n/n G =0.85 J. Ongena et al., Phys.of Plas. 8 (2001) 2188

JET Elmy H mode / After puff/ Ar accumulation The after puff phase features higher particle confinement time and density peaking. With strong Ar puffing -q(0) increases, - sawtooth amplitude decreases - Ar accumulates - confinement degrades - sometimes radiative collapse is reached -. W. Suttrop et al., Phys.of Plas.9 (2002) 2103

JET Elmy H mode / After puff/ Effect of ICRH Moderate (2-3 MW against MW of NBI) ICRH power deposited in the center: Heats the plasma core (Te peaks)-> Screens impurity Increases diffusion ( ne flattens) -> Opposes impurity peaking Keeps q(0) below 1 - maintains sawteeth -> Contribute to expel Ar Altogether sustains the anomalous transport -> Reduces impurity accumulation M.F Nave et al. To be published

JET Elmy H mode / After puff/ Effect of ICRH Ar density profiles reconstructed by a 1-D Collisional Radiative Transport Code (Mattioli’s) Septum, low  w/o ICRH Septum, low  with 2 MW ICRH

JET Elmy H mode / After puff/ Effect of ICRH EHT, Continuous D2 Puffing, with 2 MW ICRH Best radiation belt. Possible contribution from CX

JET Elmy H mode / After puff/ Effect of ICRH D’s and V’s (from Mattioli’s impurity transport model) Accumulation - Strong inward convection No accumulation : convection may become outward M.E. Puiatti et al.Plas. Phys.Contr. Fus. 44(2002)1863 In shots in which accumulation is avoided Anomalous transport increases Inward convection decreases and may become outward

JET Elmy H mode / After puff/ Effect of ICRH Neoclassical transport parameters In both cases, with and without accumulation, transport is anomalous, but in the shot with accumulation the empirical peaking factor is “closer” to the neoclassical one than in the case w/o accumulation.

JET Elmy H mode / After puff/ Effect of ICRH

JET Elmy H mode / After puff/ Effect of Sawteeh Impurity transport model results : Sawteeth contribute to the expulsion of the impurities from the core M.Mattioli et al.EPS meeting Montreaux 2002

JET Elmy H mode / After puff/ Effect of Sawteeh However their sole contribution does not justify the absence of Ar accumulation : other mechanisms are present

JET Elmy H mode / After puff/ Effect of continuous modes Other MHD activity in the form of continuous modes - m=1 n=1 and others -helps increasing the anomalous transport. M.Mattioli et al.EPS meeting Montreaux 2002

Radiatively improved mode in FTU In FTU ohmic Ne seeded plasmas RI-Mode avoids saturation of confinement with density. Typical signatures Ne profiles peak Electron and ion temperature increase (for the same input power) As a consequence, confinement improves (x1.4)

Radiatively improved mode in FTU D.Frigione, L. Pieroni et al. EPS Montreaux, 2002

Radiatively improved mode in FTU

In Ne seeded shots metal concentration (Fe, Ni, Mo) decreases This appears to be due to a reduced sputtering associated with the reduced convected /conducted power through the edge (  rad ~.85). FTU has TZM (Mo alloy) limiters L.Carraro et al. EPS Montreaux 2002

Radiatively improved mode in FTU Impurity transport does not change significantly (same v’s and D’s) give satisfactory simulation results in both shots with and without seeding) Impurity transport is anomalous: neoclassical diffusion in the core ~ 0.02 m 2 s -1 Accumulation is avoided by a reduction of the influx

Conclusions In High density regimes impurity seeded discharges impurity accumulation can be avoided. IN JET: The risk of impurity accumulation with Ar seeding is avoided by modifying transport. Adding central deposited ICRH on top of NBI heats the core and maintains q(0) below 1 and flat. IN FTU : The radiation belt in Ne seeded D plasmas avoids the risk of impurity accumulation by reducing significantly the metal influx, with no major modification of the impurity transport. FUTURE WORK 1) Extend the analysis to other High Density scenarios 2) Investigate detailed transport mechanisms