LH Generated Hot Spots on the JET Divertor

Slides:



Advertisements
Similar presentations
Progress with PWI activities at UKAEA Fusion GF Counsell, A Kirk, E Delchambre, S Lisgo, M Forrest, M Price, J Dowling, F Lott, B Dudson, A Foster,
Advertisements

1 TORE SUPRA Association Euratom-Cea A. Ekedahl et al Progress Report DITS project : 13 July 2007 Operational Limits during the TPL Deuterium Loading Experiment.
Institute for Plasma Physics Rijnhuizen D retention in W and mixed systems in Pilot-PSI G. De Temmerman a, K. Bystrov a, L. Marot b, M. Mayer c, J.J. Zielinski.
1 1 – Experience of diagnostics used for LH grill protection 2 – Layout of the suitable diagnostics in ITER 3 – Info on fibre optics for wave guide arc.
Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
ASIPP HT-7 belt limiter Houyang Guo, Sizhen Zhu and Jiangang Li Investigation of EAST Divertor Asymmetry in Plasma Detachment & Target Power Loading Using.
ASIPP Characteristics of edge localized modes in the superconducting tokamak EAST M. Jiang Institute of Plasma Physics Chinese Academy of Sciences The.
First Wall Heat Loads Mike Ulrickson November 15, 2014.
TORE SUPRA Association EURATOM-CEA Département de Recherches sur la Fusion Contrôlée CEA - CADARACHE Saint-Paul-lez-Durance FRANCE Nonlinear LH Wave.
Effects of ICRF conditioning on the first wall in LHD N. Ashikawa, K. Saito, T. Seki, M. Tokitani, Y. Ohtawa 1), M. Nishiura, S. Masuzaki K. Nishimura.
PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 1 LHCD and Coupling Experiments with an ITER- like PAM.
A. Kirk, 20th IAEA Fusion Energy Conference, Vilamoura, Portugal, 2004 The structure of ELMS and the distribution of transient power loads in MAST Presented.
ESS 7 Lecture 14 October 31, 2008 Magnetic Storms
LH SOL generated fast particles meeting, Prague, Dec 2004 J. Mailloux JET Programme 2005 Selected issues that could affect LH experiments.
G. De Temmerman ITPA 10 meeting, Moscow, April 06 1 Influence of material choice on the deposition/erosion mechanisms affecting optical reflectivity of.
PFC meeting 9-11 May 2005 PPPL CDX-U E-beam experiments on CDX-U Presented by Dick Majeski R. Kaita, T. Gray, H. Kugel, J. Spaleta, J. Timberlake, L. Zakharov.
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.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
1 Garching, 20/3 2009EFDA Fuelling Meeting A Ekedahl 1, M Goniche 1, G Granucci 2, J Mailloux 3, V Pericoli 4, V Petrzilka 5, K Rantamäki 6, JET-EFDA contributors,
Initial wave-field measurements in the Material Diagnostic Facility (MDF) Introduction : The Plasma Research Laboratory at the Australian National University.
Overview the CASTOR “Fast Particles” experiments A: F. Zacek 1, V. Petrzilka 1, M. Goniche 2, P. Devynck 2, J. Adamek 1 1 Association Euratom/IPP.CR, Za.
1 Association Euratom-Cea TORE SUPRA Tore Supra “Fast Particles” Experiments LH SOL Generated Fast Particles Meeting Association Euratom IPP.CR, Prague.
Simulation Study on behaviors of a detachment front in a divertor plasma: roles of the cross-field transport Makoto Nakamura Prof. Y. Ogawa, S. Togo, M.
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.
Edge Localized Modes propagation and fluctuations in the JET SOL region presented by Bruno Gonçalves EURATOM/IST, Portugal.
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
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.
10th ITPA conference, Avila, 7-10 Jan Effects of High Energy Ions Accelerated in front of ICRF Antennas in LHD S. Masuzaki on behalf of the LHD Experimental.
Complex Plasmas as a Model for the Quark-Gluon-Plasma Liquid
Introduction to Plasma- Surface Interactions Lecture 3 Atomic and Molecular Processes.
RF simulation at ASIPP Bojiang DING Institute of Plasma Physics, Chinese Academy of Sciences Workshop on ITER Simulation, Beijing, May 15-19, 2006 ASIPP.
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.
Advances In High Harmonic Fast Wave Heating of NSTX H-mode Plasmas P. M. Ryan, J-W Ahn, G. Chen, D. L. Green, E. F. Jaeger, R. Maingi, J. B. Wilgen - Oak.
D. Tskhakaya et al. 1 (13) PSI 18, Toledo July 2008 Kinetic simulations of the parallel transport in the JET Scrape-off Layer D. Tskhakaya, R.
Study of NSTX Electron Density and Magnetic Field Fluctuation using the FIReTIP System K.C. Lee, C.W. Domier, M. Johnson, N.C. Luhmann, Jr. University.
Edge-SOL Plasma Transport Simulation for the KSTAR
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.
Session I-B – Overview Talks Lithium in Magnetic Confinement Experiments S. MirnovLi collection experiments on T-11M and T-10 in framework of Li closed.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.
A. Vaivads, M. André, S. Buchert, N. Cornilleau-Wehrlin, A. Eriksson, A. Fazakerley, Y. Khotyaintsev, B. Lavraud, C. Mouikis, T. Phan, B. N. Rogers, J.-E.
D. Tskhakaya, LH SOL Generated Fast Particles Meeting IPP.CR, Prague December 16-17, 2004 Quasi-PIC modelling of electron acceleration in front of the.
1 LHCD Properties with a New Lower Hybrid Wave Antenna on HT-7 Tokamak Wei Wei,Guangli Kuang,Bojiang Ding,Weici Shen and HT-7 Team Institute of Plasma.
ASIPP, 24/ Modelling of near LH effects on the SOL, in view of extrapolation to ITER V. Petrzilka 1, G. Corrigan 2, P. Belo 3, A. Ekedahl 4, K.
Summary of RF-Related Presentations at the 2011 EPS Meeting G. Taylor NSTX Physics Meeting July 25, 2011 NSTX Supported by 1.
1Field-Aligned SOL Losses of HHFW Power and RF Rectification in the Divertor of NSTX, R. Perkins, 11/05/2015 R. J. Perkins 1, J. C. Hosea 1, M. A. Jaworski.
1 Nuclear Fusion Class : Nuclear Physics K.-U.Choi.
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)
HHFW heating experiments in NSTX S. Bernabei, J. Hosea, B. LeBlanc, C. K. Phillips, P. Ryan, D. Swain, J. R. Wilson and the whole NSTX crew. ORNL.
1 Comments to and conclusions drawn from RFA measurements made on April 5 (Friday) and April 9 (Tuesday) 2002 on JET, campaign C5 (K. Erents, M. Goniche,
Stochastic wake field particle acceleration in Gamma-Ray Bursts Barbiellini G., Longo F. (1), Omodei N. (2), Giulietti D., Tommassini P. (3), Celotti A.
Lower Hybrid Wave Coupling and Current Drive Experiments in HT-7 Tokamak Weici Shen Jiafang Shan Handong Xu Min Jiang HT-7 Team Institute of Plasma Physics,
Member of the Helmholtz Association Meike Clever | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ Graduiertenkolleg 1203 Dynamics.
T. Biewer, Sep. 20 th, 2004 NSTX Results Review of 11 Edge Ion Heating by Launched HHFW in NSTX T.M. Biewer, R.E. Bell, S. Diem, P.M. Ryan, J.R.
Mechanisms for losses during Edge Localised modes (ELMs)
Study on Monatomic Fraction Improvement with Alumina Layer on Metal Electrode in Hydrogen Plasma Source Bong-Ki Jung, Kyung-Jae Chung, Jeong-Jeung Dang,
Temperature Measurements of Limiter Surfaces at High Heat Flux in the HT-7 Tokamak H. Lin, X.Z. Gong, J. Huang, J.Liu, B. Shi, X.D. Zhang, B.N. Wan,
Features of Divertor Plasmas in W7-AS
Ex/4-3: On the challenge of plasma heating in the JET Metallic Wall
Progress Toward Measurements of Suprathermal Proton Seed Particle Populations J. Raymond, J. Kohl, A. Panasyuk, L. Gardner, and S. Cranmer Harvard-Smithsonian.
Recycling and impurity retention in high-density,
Generation of Toroidal Rotation by Gas Puffing
Finite difference code for 3D edge modelling
Secondary divertor heat and particle flux
ITER consequences of JET 13C migration experiments Jim Strachan, PPPL Jan. 7, 2008 Modeled JET 13C migration for last 2 years- EPS 07 and NF paper in prep.
J.R. Wilson, R.J. Goldston, J.C. Hosea ReNew Theme III Workshop
Application to the VIS/IR Imaging System of ITER
Instructor: Gregory Fleishman
-Short Talk- The soft X-ray characteristics of solar flares, both with and without associated CMEs Kay H.R.M., Harra L.K., Matthews S.A., Culhane J.L.,
Near-Field Physics of Lower-Hybrid Wave Coupling to Long-Pulse, High Temperature Plasmas in Tore Supra A dynamic Stark effect measurement performed near.
Presentation transcript:

LH Generated Hot Spots on the JET Divertor K.M. Rantamäki1, V. Petržílka2, F. Žáček2, A. Ekedahl3, K. Erents4, V. Fuchs2, M. Goniche3, G. Granucci5, S.J. Karttunen1, J. Mailloux4, and M.-L.Mayoral4 1Association Euratom - Tekes 2Association Euratom - IPP-CZ 3Association Euratom - CEA 4Association Euratom - UKAEA 5Association Euratom-ENEA

Introduction During LHCD on Tore Supra and TdeV strong localised heat loads have been observed on components that are magnetically connected to the grill region. A probable reason for the hot spots are the electrons accelerated in front of the LH grill by parasitic absorption of LH power. ions accelerated by the charge separation field The fast particle problem is most pronounced during a high power LHCD experiment. There were good reasons to believe that hot spots also exist on JET. Purpose was to get direct or indirect evidence of the fast particles created by parasitic absorption of LH power in front of the grill. The long term aim is to understand the mechanism behind parasitic generation of fast particles. In order to find a way to avoid the hot spots, it is necessary to find the parameters that control their formation.

Hot Spots on JET Hot spots in locations magnetically connected to the JET LH grill mouth were first seen on videos from shots 37338, 38804-5 [Goniche et al. JET-R(97)14]. Low q, q95  3.1 Short magnetic field connection Hot spots on outer divertor apron Brighter spots when grill behind the limiter ? #37338@63.56s Rgrill - Rpol.lim. = 0 #37338@65.28s Rgrill -Rpol.lim. = 2 cm CCD images for F = 5.3 1021el/s and PLH = 2.5 MW

Spots on the inner apron The Infra Red Movie Analyser IRMA software was used to analyse the CCD videos of the shots that showed hot spots on the divertor apron. The analysis shows clear increases in the brightness of the measuring points in the second phase of the shots with clear correlation with the end of the hot spots and the LH power. The ELM activity can be seen very clearly as sharp peaks in the background brightness.

Spots on the outer apron The IRMA analysis also showed hot spots on the outer apron. The drop of the brightness agrees very well with the end of the LH power. The increase in the brightness at the red and black measuring points starts at about t=51 s and ends when the LH power end at t=52.5 s.

Trends of the Hot Spots Behaviour Experimental observations at Tore Supra and TdeV indicate a dependence on the LH power and the edge density. Simulations suggest also a dependence on the edge temperature. Experiments at JET indicate that the hot spots are weaker when operating at large distance. The density in front of the launcher is lower (coupling was similar, however). The propagation of the particle beam further away from the launcher in a less dense plasma is different (due to instabilities).

Consequences for ITER At nominal power density for ITER (33 MW/m2), the parallel heat flux is expected to be less than 7 MW/m2 at edge density is lower than 0.61018m-3. This flux is easily manageable for ITER plasma-facing components except for Be first wall, which will require alignment of field lines to the wall within 2.5°. Significant reduction of the heat flux could result from a reduction of the high-N|| content of the spectrum launched by the PAM. LHCD experiments with a distance up to 10 cm between the last closed flux surface and the antenna have shown that increasing this distance to ITER-relevant conditions has a beneficial effect on the heat flux deposition.

Further work A few good reference pulses found. We should get a better understanding of conditions in which the hot spots appear at a given location Dependence of the intensity of the hot spots on parameters like plasma density (difficult – gas puffing!), LH power, grill position, ROG, etc., should be further investigated. Better statistics (more shots) would be needed to confirm tendencies shown on the previous slide. The hot spots should be brought into the IR camera view to find the thermal loads that they cause. Direct the fast particle beam into the RFA slit at low LH powers (not to damage the RFA) in order to find whether the fast ions participate in the heating (and in erosion – sputtering). May be not just piggy-back experiments only?