Proposal #2: AT scenarios, Rerun 600 and 450 kA discharges with PLH = 1 MW C. Kessel,  PPPL Previous discharges with varying rampups at 600 and 450.

Slides:



Advertisements
Similar presentations
Physics Basis of FIRE Next Step Burning Plasma Experiment Charles Kessel Princeton Plasma Physics Laboratory U.S.-Japan Workshop on Fusion Power Plant.
Advertisements

P A C I F I C C O N C O U R S E D R. S U I T E L O S A N G E L E S, C A P | F | E I.
Stability, Transport, and Conrol for the discussion Y. Miura IEA/LT Workshop (W59) combined with DOE/JAERI Technical Planning of Tokamak Experiments (FP1-2)
ASIPP Characteristics of edge localized modes in the superconducting tokamak EAST M. Jiang Institute of Plasma Physics Chinese Academy of Sciences The.
D. R. Mikkelsen, ITPA Transport & Confinement Topical Group Workshop, Milan October 2008 Validation of ITER Simulation Models ITER requests help.
NSTX S. A. Sabbagh XP615: Active Stabilization of the Resistive Wall Mode at Low Aspect Ratio  Goals (Part I):  Operate new RWM feedback system on 0.9–1.0.
Changing the absorbers: how does it fit in the MICE experimental programme? Besides the requirement that the amount of multiple scattering material be.
ARIES-ACT1 preliminary plasma description C. Kessel, PPPL ARIES Project Meeting, October 13, 2011.
C. Kessel Princeton Plasma Physics Laboratory For the NSTX National Team DOE Review of NSTX Five-Year Research Program Proposal June 30 – July 2, 2003.
Analysis and Simulations of the ITER Hybrid Scenario C. Kessel, R. Budny, K. Indireshkumar Princeton Plasma Physics Laboratory, USA ITPA Topical Group.
Advanced Tokamak Regimes in the Fusion Ignition Research Experiment (FIRE) 30th Conference on Controlled Fusion and Plasma Physics St. Petersburg, Russia.
Integrated Modeling and Simulations of ITER Burning Plasma Scenarios C. E. Kessel, R. V. Budny, K. Indireshkumar, D. Meade Princeton Plasma Physics Laboratory.
1 CHI Summary Transient CHI (XP606) –All systems operated reliably without any faults Edge Current drive (XP533)
Mid-Run Assessment - ISD S. Kaye, D. Gates 10 May 2006.
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.
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.
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.
PF1A upgrade physics review Presented by D. A. Gates With input from J.E. Menard and C.E. Kessel 10/27/04.
1 Instabilities in the Long Pulse Discharges on the HT-7 X.Gao and HT-7 Team Institute of Plasma Physics, Chinese Academy of Sciences, P.O.Box 1126, Hefei,
D. A. Rasmussen, NCSX Research Forum 2006 Page 1 ECH and Fast Wave Electron Heating Systems for NCSX Tim Bigelow, Dave Rasmussen, Phil Ryan, Mike Cole.
1 Confinement Studies on TJ-II Stellarator with OH Induced Current F. Castejón, D. López-Bruna, T. Estrada, J. Romero and E. Ascasíbar Laboratorio Nacional.
Simulation and Analysis of the Hybrid Operating Mode in ITER C. Kessel, R. Budny, and K. Indireshkumar Princeton Plasma Physics Laboratory Symposium On.
ASIPP YOUNIS Jawad, WAN Baonian, LIN Shiyao, SHI Yuejiang, and HT-7 Team HT-7 Study of LHW current drive efficiency and fast electron distribution.
ASIPP Long pulse and high power LHCD plasmas on HT-7 Xu Qiang.
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.
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.
Terms to know by the end of the unit: Image obtained from:
Work with TSC Yong Guo. Introduction Non-inductive current for NSTX TSC model for EAST Simulation for EAST experiment Voltage second consumption for different.
RFX-mod programme workshop, January 2009 Scenario and operational issues for high current L. Zanotto, R. Cavazzana, S. Dal Bello, F. Milani.
1 Columbia U Comp-X General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics NYU ORNL PPPL PSI SNL UC Davis UC Irvine UCLA UCSD U Maryland.
Steady State Discharge Modeling for KSTAR C. Kessel Princeton Plasma Physics Laboratory US-Korea Workshop - KSTAR Collaborations, 5/19-20/2004.
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.
Effect of 3-D fields on edge power/particle fluxes between and during ELMs (XP1026) A. Loarte, J-W. Ahn, J. M. Canik, R. Maingi, and J.-K. Park and the.
MHD Issues and Control in FIRE C. Kessel Princeton Plasma Physics Laboratory Workshop on Active Control of MHD Stability Austin, TX 11/3-5/2003.
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.
FIRE Advanced Tokamak Progress C. Kessel Princeton Plasma Physics Laboratory NSO PAC 2/27-28/2003, General Atomics 1.0D Operating Space 2.PF Coils 3.Equilibrium/Stability.
Advanced Tokamak Modeling for FIRE C. Kessel, PPPL NSO/PAC Meeting, University of Wisconsin, July 10-11, 2001.
FY WEP TSG Goals & WEP-Relevant Diagnostic Upgrades NSTX Supported by WEP TSG Meeting September 14,
1 Columbia U Comp-X General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics NYU ORNL PPPL PSI SNL UC Davis UC Irvine UCLA UCSD U Maryland.
Simulation of Non-Solenoidal Current Rampup in NSTX C. E. Kessel and NSTX Team Princeton Plasma Physics Laboratory APS-DPP Annual Meeting, Savannah, Georgia,
Integrated Plasma Simulations C. E. Kessel Princeton Plasma Physics Laboratory Workshop Toward an Integrated Plasma Simulation Oak Ridge, TN November 7-9,
Status of NSTX/DIII-D/MAST aspect ratio core confinement comparison studies M. Peng, for E.J. Synakowski For the ITPA Transport Physics Working Group Kyota,
T. Biewer, Sep. 21 st, 2004 NSTX Results Review of 11 Dependence of Edge Flow on Magnetic Configuration in NSTX T.M. Biewer, R.E. Bell, D. Gates,
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,
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
海港自由貿易港區及自由經濟示範區之加值作業
High-beta Program 3 June 2002 Objective: Investigate effect of toroidal currents on high-b performance: 1. Low-iota: discharges with current ramp and constant.
Charge Exchange Analysis Diagnostic Development
Asymmetries in density profiles?
Advanced Scenarios: ITER-like Hybrid at Low Bt without LH
GHz reflectometer to be operated in X-mode
A.D. Turnbull, R. Buttery, M. Choi, L.L Lao, S. Smith, H. St John
High Bootstrap Fraction Plasmas with ITBs
Investigation of triggering mechanisms for internal transport barriers in Alcator C-Mod K. Zhurovich C. Fiore, D. Ernst, P. Bonoli, M. Greenwald, A. Hubbard,
Proposal #3: Expand ITER rampdown cases
Diagnosis of Pellet Induced Bootstrap Current with Alfvén Cascades
Lower Ip Long Pulse H+ITB Advanced Scenarios
Lower Ip Long Pulse L-mode and H-mode Advanced Scenarios
Integrated Operation of Steady-state Long Pulse H-mode in EAST
C. Kessel, PPPL Standard breakdown is done at 5.4 T
The Doppler Effect.
75 previous answer What is of 37.5? ? go to.
Application of Proposed New BES Definition:
Low Charge Scenarios.
75 previous answer What is of 60? ? go to.
Ioffe Summary Fast MHD oscillations observed on the TUMAN-3M in absence of energetic ions Bursts of the oscillations correlate with saw-tooth crashes and.
Beam Ion Performance and Power Loads in the ITER Pre-Fusion Power Operating Scenarios (PFPO) with Reduced Field and Current We have used ASCOT to simulate.
Locked mode Induced Disruption and Avoidance
Presentation transcript:

Proposal #2: AT scenarios, Rerun 600 and 450 kA discharges with PLH = 1 MW C. Kessel,  PPPL Previous discharges with varying rampups at 600 and 450 kA all obtained ≈ 0.5 MW of LH power for 0.5 s In 2009, access to 1 MW of LH power would change several observations significantly due to stronger current profile modifications Select several cases from previous expts to redo at the higher power In 2010, possibly extend to longer LH pulses with 1 or more MW of LH power, this allows us to maintain the LH power as we enter ICRF induced H-modes