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

Slides:



Advertisements
Similar presentations
Joint SEWGs-TFE meeting S. Brezinsek22/07/2008 TF E Impact of N 2 on carbon chemistry in JET S. Brezinsek, Y. Corre and TFE.
Advertisements

How does energy transfer through our atmosphere?
Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
9th TTF Spain September 11, 2002 B. J. Peterson, NIFS, Japan page 1 Radiative Collapse and Density Limit in the Large Helical Device.
Chalkidikhi Summer School Plasma turbulence in tokamaks: some basic facts… W.Fundamenski UKAEA/JET.
A. Kirk, 21 st IAEA Fusion Energy Conference, Chengdu, China, October 2006 Evolution of the pedestal on MAST and the implications for ELM power loadings.
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.
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.
Fins Design Project. Problem Does adding fins to the heating coil of a conventional oven significantly reduce the time required to heat the oven? Objectives.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
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.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
Predictive Integrated Modeling Simulations Using a Combination of H-mode Pedestal and Core Models Glenn Bateman, Arnold H. Kritz, Thawatchai Onjun, Alexei.
Study of the pedestal dynamics and stability during the ELM cycle A. Burckhart Advisor: Dr. E. Wolfrum Academic advisor: Prof. Dr. H. Zohm MPI für Plasmaphysik,
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)
Profile Measurement of HSX Plasma Using Thomson Scattering K. Zhai, F.S.B. Anderson, J. Canik, K. Likin, K. J. Willis, D.T. Anderson, HSX Plasma Laboratory,
J A Snipes, 6 th ITPA MHD Topical Group Meeting, Tarragona, Spain 4 – 6 July 2005 TAE Damping Rates on Alcator C-Mod Compared with Nova-K J A Snipes *,
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,
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,
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.
F. Koechl (1) IOS ITPA Meeting, Kyoto Free boundary simulations of the ITER baseline scenario and its variants F. Koechl, M. Mattei, V. Parail,
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.
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.
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
TRANSP for core particle transport studies M. Maslov.
T. Bolzonella – 9 February 2011 – RFX-mod programme workshop TF1: Physics integration for high performance RFP Proposals and discussion T. Bolzonella,
Dependence of Pedestal Structure on Ip and Bt A. Diallo, R. Maingi, S. Zweben, B.P. LeBlanc, B. Stratton, J. Menard, S. Gerhardt, J. Canick, A. McClean,
Edge Turbulence in High Density Ohmic Plasmas on NSTX K.M. Williams, S.J. Zweben, J. Boedo, R. Maingi, C.E. Bush NSTX XP Presentation Draft 5/25/06.
ContributorsEuratom Associations L. Carraro, M. Mattioli, M.E. Puiatti, P. Scarin, B. Zaniol Consorzio RFX, Padova, Italy P.DuMortier, A. Messiaen, J OngenaEcole.
Page 1 Alberto Loarte- NSTX Research Forum st - 3 rd December 2009  ELM control by RMP is foreseen in ITER to suppress or reduce size of ELM energy.
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.
IAEA-TM 02/03/2005 1G. Falchetto DRFC, CEA-Cadarache Association EURATOM-CEA NON-LINEAR FLUID SIMULATIONS of THE EFFECT of ROTATION on ION HEAT TURBULENT.
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.
Current Drive Experiments with Oscillating Toroidal Flux in HT-7 Superconducting Tokamak J.S.Mao, P. Phillips 1, J.R.Luo, J.Y.Zhao, Q.L.Wu, Z.W.Wu, J.G.Li,
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.
TFE 3/2/2004 – Fuel retention in JET - J. Bucalossi / T. Loarer Assessment of fuel retention in JET : Contingency – 2 shifts on 6 th of february E. Tsitrone.
Carlos Hidalgo Laboratorio Nacional de Fusión CIEMAT Madrid, Spain
Impact of low-Z impurities on the L-H threshold in JET
T. Tala (JET, DIII-D), W. Solomon (DIII-D, JET, NSTX), S
11th IAEA Technical Meeting on H-mode Physics and Transport Barriers" , September, 2007 Tsukuba International Congress Center "EPOCHAL Tsukuba",
Andrew Kirk on behalf of
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.
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.
Advanced Scenarios: ITER-like Hybrid at Low Bt without LH
Heat flux width scaling in ITER limiter configurations
Investigation of triggering mechanisms for internal transport barriers in Alcator C-Mod K. Zhurovich C. Fiore, D. Ernst, P. Bonoli, M. Greenwald, A. Hubbard,
Stereoscopic Pellet Imaging
Dynamics of transient divertor re-attachment
Diagnosis of Pellet Induced Bootstrap Current with Alfvén Cascades
IPP report – C. García-Rosales
TC-2 – Power ratio April 2011, San Diego
Methane Screening on C-MOD EDA ELM-mitigated Plasmas Jim Strachan, PPPL Nov. 30, 2004 Goal: compare impurity behavior in ELM mitigated plasmas – ergodic.
Lower Ip Long Pulse L-mode and H-mode Advanced Scenarios
Joint European Research Doctoral Network in Fusion Science and Engineering Edge Pedestal Profile Characteristics of H-Mode Discharges in ASDEX Upgrade.
NTM Stability at Low Collisionality
Jerry Hughes C-Mod Ideas Forum December 15, 2006
The effect of ELM pacing by vertical kicks on the access to stationary H-mode with H98~1 on JET E. de la Luna 24th.
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
First principles and integrated modelling achievements towards trustful fusion power predictions for JET and ITER Significant work performed for DT extrapolation.
IOS-6.3: Control of experimentally simulated burning state
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.
Max-Planck Institut für Plasmaphysik Garching
Automatic Analysis of Edge Pedestal Gradient Degradation during ELMs
Coupling between intrinsic rotation and turbulence-driven residual stress in the TEXTOR tokamak (Y. Xu et al, EX/P8-18) In low discharges (open.
Modelling of Transitions Between L- and H-Mode
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

Additional heating power required to access H-mode (L-H transition) Power requirements for access to H=1 H-modes and role of radiated power spatial distribution (I) Power to access good confinement in ITER subject to significant uncertainties : Additional heating power required to access H-mode (L-H transition) Margin above L-H transition power to reach H ~ 1 in stationary conditions Role of core/edge radiation on power requirement Dynamics of edge power flow evolution following H-mode transition (Pa) JET- Sartori – PPCF 2004 AUG – F. Ryter – HMW’07

Power requirements for access to H=1 H-modes and role of radiated power spatial distribution (II) Experimental plan Plasma conditions for highest Padd/Bt in C-mod with q95 ~ 3-4 and d ~ 0.5 1. Perform low/now fuelling Padd scan : L-mode to highest Padd (EDA) (3-4 shots) 2. Determine PL-H for <ne>H-mode in previous discharges (3-4 shots) 3. Repeat 1 and 2 at higher density (6-8 shots) 4. Emulate ITER H-mode access at high and low <ne> by feedback of a fraction of Padd on Wplasma (~ 50 % Padd constant + ~ 50 % Padd ~ Wplasma2) (2 shots) 5. Repeat high <ne> & H ~1 discharges from with N2, Ne, Ar(two levels) with same Pedge = Padd – Pradcore (6 shots)