SUMMARY Topic A: Toroidal systems Topic D: Theory &numerical modelling G.Van Oost 17th IAEA...

Post on 15-Jan-2016

216 views 0 download

Tags:

Transcript of SUMMARY Topic A: Toroidal systems Topic D: Theory &numerical modelling G.Van Oost 17th IAEA...

SUMMARY

Topic A: Toroidal systems

Topic D: Theory &numerical modelling

G.Van Oost

17th IAEA Technical Meeting on Research Using Small Fusion DevicesLisbon, 22 to 24 October 2007

Progress on Joint Experiments on Small Tokamaks and other Activities within the IAEA

CRP on “Joint Research Using Small Tokamaks”

• M Gryaznevich1 , E. Del Bosco2 , G. Van Oost3, A. Malaquias4, G. Mank4

• for the CRP “Joint Research Using Small Tokamaks” team

• 1EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, UK

• 2 INPE, São José dos Campos, Brazil• 3 Department of Applied Physics, Ghent University, Ghent, Belgium

• 4IAEA, NAPC Physics Section, Vienna, Austria• E-mail: mikhail.gryaznevich@ukaea.org.uk.

• 1EURATOM/UKAEA Fusion Association, Culham SC, Abingdon, UK

Contributions from small plasma devices to the ITER project

Dhiraj Bora

ITER Organization, Cadarache, France

17th IAEA Technical Meeting on Research Using Small Fusion DevicesLisbon, 22 to 24 October 2007

Joint Experiments on the tokamaks CASTOR and T-10

Department of Applied PhysicsGhent University

B- 9000 GentBelgium

Presented by Guido Van OostFor the CRP “Joint Research

Using Small Tokamaks” teams

G Van Oost1, M Gryaznevich2, E Del Bosco4, A Malaquias6, G Mank6 , M Berta5, 13, J Brotankova3, R Dejarnac3, E Dufkova3, I Ďuran3, M Hron3, P Peleman1, J Sentkerestiova3, J Stöckel3, B Tál5, V Weinzettl3, J Zajac3, S Zoletnik5, V Budaev11, N Kirneva11, G Kirnev11, B Kuteev11, A Melnikov11, M Sokolov11, V Vershkov11, I El Chama Neto15, J Ferreira4, R Gonzales14, C R Gutierrez Tapia18, H Hegazy8, P Khorshid12, A W Kraemer-Flecken16, L I Krupnik19 ,Y Kuznetsov7, A M Marques Fonseca17, A Ovsyannikov9, L Ruchko7, E Sukhov9, A Singh10, V Soldatov16, A Talebitaher12, , G M Vorobjev9

1Dep. of Applied Physics, Ghent Univ., Belgium; 2EURATOM/UKAEA Fusion Association, Culham SC, Abingdon, UK;

3Institute of Plasma Physics, Association EURATOM/IPP, Czech Rep.; 4INPE, São José dos Campos, Brazil; 5KFKI-

RMKI, Association EURATOM, Budapest, Hungary; 6IAEA, NAPC Physics Section, Vienna, Austria; 7Institute of

Physics, Univ. of São Paulo, Brazil; 8EAEA, Cairo, Egypt; 9Saint Petersburg State Univ., Russia; 10Plasma Physics

Lab., Univ. of Saskatchewan, Canada; 11RRC “Kurchatov Institute”, Moscow, Russia; 12Plasma Physics Research

Center, Teheran, Iran; 13Széchenyi István Univ., Association EURATOM, Győr, Hungary; 14CICATA-IPN, Mexico;

15Univ. Tuiuti Paraná, Brazil; 16Forschungszentrum, Julich, Germany; 17IST, Lisbon, Portugal; 18ININ, Mexico;

19Phys-Tech Inst., Kharkov, Ukraine

Modern tokamak (operational in Culham Laboratory, UK until 2002)

Offered to IPP- ASCR, Prague

R.Panek, M.Hron: Tokamak COMPASS

23 rd October 2007 17-th IAEA TM on RUSFD Lisbon

17-th IAEA TM on RUSFD Lisbon, 23-rd of October 2007

The study of GAM properties in The study of GAM properties in the T-10 tokamakthe T-10 tokamak

A.V. Melnikov1, L.G. Eliseev1, S.V. Perfilov1, S.E. Lysenko1, S.A.Grashin1,V.A. Mavrin1, R.V. Shurygin1, D.A. Shelukhin1, V.A. Vershkov1, V.P. Budaev1,G.N. Tilinin1, S.A. Grashin1, L.I. Krupnik2, A.D. Komarov2, A.S. Kozachek2, A. Kraemer-Flecken3, S.V. Soldatov3, G. Ramos4, C.R. Gutierrez-Tapia5,

H. Hegazy6, A. Singh7, J. Zajac8, G. Van Oost9 and M. Gryaznevich10

1 Nuclear Fusion Institute, RRC "Kurchatov Institute", 123182, Moscow, Russia,2 Institute of Plasma Physics, NSC “Kharkov Institute of Physics and Technology”, Kharkov, Ukraine3 Institut für Plasmaphysik, Forschungszentrum Jülich, EURATOM Association, Jülich, Germany4 CICATA, Instituto Politécnico Nacional, Mexico5 Instituto Nacional de Investigaciones Nucleares, Mexico6 Egyptor project, Egypt7 University of Saskatchewan, Canada8 Institute of Plasma Physics, Prague, Czech Republic9 Ghent University, Belgium

IAEA Joint Experiment at RRC “ Kurchatov Institute”

Overview of recent ISTTOK results

C. Silva, H. Fernandes, C.A.F. Varandas, D. Alves, B.B. Carvalho, I. Carvalho, P. Carvalho, P.A.

Carvalho, R. Coelho, A. Duarte, P. Duarte, J. Ferreira, H. Figueiredo, J. Figueiredo, J. Fortunato, R.

Gomes, B. Gonçalves, I. Nedzelskij, A. Neto, T. Pereira, V. Plyusnin, D. Valcárcel

Associação Euratom/IST, Centro de Fusão Nuclear, Instituto Superior Técnico

1049-001 Lisboa, Portugal

A. Sharakovski, O. Lielausis, A. Klyukin, E. Platacis, I. TaleAssociation EURATOM/University of Latvia, Institute of Solid State Physics,

Riga, Latvia

T. LuntHumboldt-Universitat zu Berlin, Berlin, Germany

Control and data acquisition

Edge plasma physics

Study of fusion relevant materials

Diagnostics

JE 3 on ISTTOK

Recent results from the STOR-M tokamak

M. Dreval, S. Elgriw, O. Mitarai(1), A. Pant, D. Rohraff, A.K. Singh(2) D. Trembach, C.Xiao,A. Hirose

Plasma Physics Laboratory, Department of Physics and Engineering Physics, University of Saskatchewan, Canada. e-mail: akira.hirosei@usask.ca

(1) Institute of Industrial Science and Technical Research, Kyushu Tokai University, Kumamoto, Japan. (2) Dept. of Physics, Utah State Univ., Logan, Utah, USA.

CT injection and MHD Simulation of OH Current Start-Up in Iron-Core ST

CONCLUSIONS JE’s ( IAEA CRP)• These first Joint Experiments have clearly demonstrated that small

tokamaks are suitable and important for broad international cooperation, providing the necessary environment and manpower to conduct dedicated joint research programmes.

• The contribution of small tokamaks to the mainstream fusion research such as edge turbulence, improved confinement, and diagnostics development can be enhanced through coordinated planning.

• The activities under this IAEA Coordinated Research Project are already paying visible dividends both in increased number of publications and improved collaboration between participating tokamak teams.

• Another important result of joint experiments is the improvement in understanding and communications between scientists from different countries, creating efficient team work both during experiments and data analysis.

• Education & Training

European Master In Nuclear Fusion Science and Engineering Physics

Negative Ion based Heating and Diagnostic Neutral Beams for ITER

B. Schunke, D. Bora, R. Hemsworth, A. Tanga, et al.

ITER Organisation, ITER Organisation – Cadarache, 13108 St.-Paul-lez-Durance, France

beatrix.schunke@iter.org

Recent Experiment Results during electron cyclotron heating on HL-2A

Y.B.Dong, H.J.Sun, Jun Zhou, W.W.Xiao, L.H.Yao, B.B.Feng, Yi Liu, J.Rao , Q.W.Yang , X.T.Ding ,

Yong Liu , and C.H.Pan

Southwestern Institute of Physics (SWIP), P.O Box 432, Chengdu 610041, China

Runaway electron-loss induced negative and positive loop voltage spikes in

Aditya Tokamak

Bhooshan Paradkar, J. Ghosh, R. L. Tanna, P. K. Chattopadhyay, D. Raju, S. B. Bhatt, C. V. S. Rao, R.

Jha, P. K. Atrey, P. Vasu, Y. C. Sexena, I. Bandopadhyay, P. K. Kaw and Aditya Team

Institute for Plasma Research, Bhat, Gandhinagar 382428, India

Modelling results match well with observed spiked in loop voltage

Fluid Model of Electron Cyclotron Current Drive

G.O. LudwigAssociated Plasma Laboratory, National Space

Research Institute

12227-010 São José dos Campos, SP, Brazil

A theory was recently advanced to describe the dynamics of electron cyclotron current drive (ECCD) using a simple macroscopic model.

One expects to apply the model to the study of both instabilities in

ECCD and synergy effects with other current drive means.

3DMAPTOR code for mapping toroidal magnetic field lines in three dimensions

J.Julio E. Herrera-Velázquez

Instituto de Ciencias Nucleares, Universidad Nacional Autónoma de México, Apdo. Postal 70-543, Ciudad

Universitaria, Delegación Coyoacán, 04511México, D.F. México

Study on electron collisions with Zn-like W ion

A. Mihailescu, V. Pais, M.C. Totolici, V. Stancalie

National Institute for Laser, Plasma & Radiation Physics, Laser. Dept., P.O.Box MG-36,Bucharest, 077125 ROMANIA, Association Euratom MEdC

MODELING OF PARTICLE TRANSPORT ON CHANNELS AND GAPS

EXPOSED TO PLASMA FLUXES

Martin Nieto-Pérez

Instituto Tecnológico de Toluca

Av. Tecnologico S/N Col. La Virgen

Metepec, Mexico, 52140 MEXICO

Predictive Simulations of Small Tokamak Experiments using BALDUR Integrated

Predictive Modeling Code

T. Onjun1, A. Boonkajay1, O. Onjun2, N. Poolyarat3 and A. Pankin4

1 Sirindhorn International Institute of Technology, Thammasat University, Klongluang, Pathumthani, Thailand

2 Department of Science Service, Bangkok, Thailand3 Department of Physics, Thammasat University,

Pathumthani, Thailand4 Department of Physics, Lehigh University, Bethlehem,

Pennsylvania, USA