Species Effects on the H-mode Threshold and ELM Behavior in H(He3) and He4(H) Plasmas in C-Mod J A Snipes, P Lamalle ITER Organization.

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

ASIPP Characteristics of edge localized modes in the superconducting tokamak EAST M. Jiang Institute of Plasma Physics Chinese Academy of Sciences The.

The Physics Base for ITER and DEMO Hartmut Zohm Max-Planck-Institut für Plasmaphysik, Garching, Germany EURATOM Association Hauptvortrag given at AKE DPG.

Yves Martin Centre de Recherches en Physique des Plasmas Association Euratom - Confédération Suisse Ecole Polytechnique Fédérale de Lausanne (EPFL) CH.

Emmanuel JoffrinXXth Fusion Energy Conference, November The « hybrid » scenario in JET: towards its validation for ITER E. Joffrin, A. C. C. Sips,

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.

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

Recent JET Experiments and Science Issues Jim Strachan PPPL Students seminar Feb. 14, 2005 JET is presently world’s largest tokamak, being ½ linear dimension.

Prof. F.Troyon“JET: A major scientific contribution...”25th JET Anniversary 20 May 2004 JET: A major scientific contribution to the conception and design.

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,

Title – Arial between 80 and 100pt Authors names Arial 50pt, A. N Other 1, 1 Associations Arial 28 pt 2 EURATOM/Culham Fusion Association, Culham Science.

1 OVERVIEW OF ITER PHYSICS V. Mukhovatov 1, M. Shimada 1, A.E. Costley 1, Y. Gribov 1, G. Federici 2,A.S. Kukushkin 2, A. Polevoi 1, V.D. Pustovitov 3,

Japan Atomic Energy Agency, Naka Fusion Institute H モード周辺プラズマの無次元量解析 Japan Atomic Energy Agency 浦野創原子力機構那珂核融合研究所.

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.

Global Stability Issues for a Next Step Burning Plasma Experiment UFA Burning Plasma Workshop Austin, Texas December 11, 2000 S. C. Jardin with input from.

A.Lyssoivan – 18PSI, Toledo, Spain 27/05/ Influence of Toroidal and Vertical Magnetic Fields on Ion Cyclotron Wall Conditioning in Tokamaks Presented.

Introduction of 9th ITPA Meeting, Divertor & SOL and PEDESTAL Jiansheng Hu

FOM - Institute for Plasma Physics Rijnhuizen Association Euratom-FOM Diagnostics and Control for Burning Plasmas Discussion All of you.

Low dimensional Edge-localised- modes dynamics in JET tokamak Edge-localised-modes characterization through data analysis Francisco A. Calderon University.

Integrated Operation Scenarios ITPA Remaining duties ITPA CC meeting & IEA/ITPA JE planning meeting –12 – 14 (15) December 2011, Cadarache –Ide, Sips and.

EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.

Hysteresis in the L-H-L transition, D C McDonald, ITPA, Princeton 20091/22 Hysterics in the L-H transition D C McDonald.

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.

PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)

Advanced Residual Analysis Techniques for Model Selection A.Murari 1, D.Mazon 2, J.Vega 3, P.Gaudio 4, M.Gelfusa 4, A.Grognu 5, I.Lupelli 4, M.Odstrcil.

Physics Analysis and Flexibility Issues for FIRE NSO PAC-2 Meeting January 17-18, 2001 S. C. Jardin with input from C.Kessel, J.Mandrekas, D.Meade, and.

Confinement & Transport Plan Classical theory of confinement and transport. o Diffusion equation Particle diffusion in a magnetic field.

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,

FIR-NTMs on ASDEX Upgrade and JET Active Control of (2,1) NTMs on ASDEX Upgrade S. Günter 1, M. Maraschek 1, M. de Baar 2, D.F. Howell 3, E. Strumberger.

Development and Assessment of “X-point limiter” Plasmas M. Bell, R. Maingi, K-C. Lee Coping with both steady-state and transient (ELM) heat loads is a.

Darren McDonald, TFS1 meeting, 20th April /20 Proposed JET 2006 confinement experiments D C McDonald Structure of talk: Hybrid studies ELMy H-mode,

Yves Martin Centre de Recherches en Physique des Plasmas Association Euratom - Confédération Suisse Ecole Polytechnique Fédérale de Lausanne (EPFL) CH.

Yves Martin Centre de Recherches en Physique des Plasmas Association Euratom - Confédération Suisse Ecole Polytechnique Fédérale de Lausanne CH

Y Andrew 1 (14) Transport and Confinement ITPA meeting October 2008 H-mode Access on JET Y Andrew and JET EFDA Contributors UKAEA- Fusion Transport.

To ‘B’ or not to ‘B’ That is the question

Some Physics Issues Related to ITER Plasma Performance

8th Meeting of the ITPA Confinement Database & Modeling Topical Group

Status of H-mode confinement Database by K. Thomsen, Kyoto, April 2005

CRYOGENICS OPERATIONS 2008 Organized by CERN

Impact of a Mock-up Ferromagnetic TBM on Plasma Operations in C-Mod

Pellet injection in ITER Model description Model validation

MHD Induced Fast Ion Loss Diagnostic for Alcator C-Mod

L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European.

2/13 Introduction Knowledge of the influence of the hydrogen isotope on H-mode confinement is essential for accurately projecting the energy confinement.

Advanced Scenarios: ITER-like Hybrid at Low Bt without LH

Comparison of Small ELM regimes A C-MOD/MAST/NSTX Multi-machine ITPA proposal Question: Is the NSTX Type V ELMy H-mode the same as a high  EDA H-mode.

Heat flux width scaling in ITER limiter configurations

TC-2 – Power ratio April 2011, San Diego

Lower Ip Long Pulse H+ITB Advanced Scenarios

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.

Additional heating power required to access H-mode (L-H transition)

Methane Screening on C-MOD EDA ELM-mitigated Plasmas Jim Strachan, PPPL Nov. 30, 2004 Goal: compare impurity behavior in ELM mitigated plasmas – ergodic.

49th Annual Meeting of APS - DPP Orlando, 11/14/2007

Lower Ip Long Pulse L-mode and H-mode Advanced Scenarios

NTM Stability at Low Collisionality

Integrated Operation of Steady-state Long Pulse H-mode in EAST

ITER ICRF Scenario Demonstration in Hydrogen with 3He Minority Heating

SOL plasma in ITER is dense and hot  thick to gas puff as in C-mod

I-mode regime has many attractive features for fusion:

First principles and integrated modelling achievements towards trustful fusion power predictions for JET and ITER Significant work performed for DT extrapolation.

(EX/P1-4) Type I ELMy H-mode in hydrogen and deuterium:

Wide-Pedestal QH-mode Initiated and Sustained with Zero Injected NBI torque throughout, and Sustained with Dominant Electron Heating (77% ECH power) Achieved.

IOS-6.3: Control of experimentally simulated burning state

Suppression of ELM’s is a major issue for ITER and beyond

Max-Planck Institut für Plasmaphysik Garching

Continued exploration of pedestal structure and edge relaxation mechanisms at lower edge collisionality J.W. Hughes, A. Hubbard, B. LaBombard, J. Terry,

An ITPA joint experiment to study

Modelling of Transitions Between L- and H-Mode

Presentation transcript:

Species Effects on the H-mode Threshold and ELM Behavior in H(He3) and He4(H) Plasmas in C-Mod J A Snipes, P Lamalle ITER Organization

What Power is Required to Reach High Confinement ? The latest H-mode threshold power scaling for deuterium plasmas is: The isotope dependence based on JET results in H, D, and D-T indicates that Pthresh  1/A for hydrogen isotopes IF this scaling holds for ITER, H-mode will not be possible with Pin = 73 MW in hydrogen and hysteresis will be required to remain in H-mode in deuterium To reach H98y2 ≥ 1, experiments indicate Pin > Pthresh is required ITER may depend on α power to sustain high confinement regimes How does the H-mode threshold change in helium? (Y. Martin, HMW 2008) 2

Can ELM Mitigation be Demonstrated in He in ITER? ASDEX Upgrade has shown: Pthresh(He) = Pthresh(D) Latest threshold powers are lower than the recent scaling More results in He would help extrapolate to ITER Robust Type I ELMy H-mode in He in ITER would allow ELM mitigation techniques to be demonstrated before the active phases This is very important for the ITER Research Plan

Species Effects on H-mode Threshold and ELM Behavior Motivation: To have more information to extrapolate H-mode power threshold and ELM behavior in H and He plasmas to ITER so that the non-active phases of ITER operation can be planned accordingly. Goals: 1) Determine how the H-mode threshold power scales in H and He. 2) Determine how the ELM behavior changes in H and He at low *. Plan of execution: Scan ne from 11020 m-3 down to 41019 m-3 in He(H) ICRF plasmas and determine the H-mode power threshold vs ne. Operate at low * and determine the ELM behavior in He (Type I ?). Repeat these experiments in H(He3) ICRF plasmas to compare. The H plasmas could be planned during the last week of operation before the next planned opening of the machine to avoid difficulties returning to D(H) ICRF operation. 2 days requested.