Clive Challis With thanks to: Doug McCune and Yuriy Baranov

Slides:



Advertisements
Similar presentations
H-mode characterization for dominant ECR heating and comparison to dominant NBI or ICR heating F. Sommer PhD thesis advisor: Dr. Jörg Stober Academic advisor:
Advertisements

Physics of fusion power
Fitting transport models to 14MeV neutron camera data D C McDonald, K D Zastrow and I Voitsekhovitch.
DPP 2006 Reduction of Particle and Heat Transport in HSX with Quasisymmetry J.M. Canik, D.T.Anderson, F.S.B. Anderson, K.M. Likin, J.N. Talmadge, K. Zhai.
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
Partially ionized gas -contains IONS, ELECTRONS and neutral particles.
Fast ion effects on fishbones and n=1 kinks in JET simulated by a non-perturbative NOVA-KN code TH/5-2Rb N.N. Gorelenkov 1), C.Z.Cheng 1), V.G. Kiptily.
Physics of fusion power Lecture 11: Diagnostics / heating.
Collisional Model in LSP. Simulation of Collisional Slowing Down of Relativistic Electrons in Plasma. A. Solodov, J. Myatt University of Rochester Laboratory.
High Energy Electron Cooling D. Reistad The Svedberg Laboratory Uppsala University.
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.
T. Hellsten IEA Burning Plasma Workshop, July 2005 Tarragona Spain Integrated Modelling of ICRH and AE Dynamics T. Hellsten, T. Bergkvist, T. Johnson and.
Chapter 5 Diffusion and resistivity
N EOCLASSICAL T OROIDAL A NGULAR M OMENTUM T RANSPORT IN A R OTATING I MPURE P LASMA S. Newton & P. Helander This work was funded jointly by EURATOM and.
1 Simulation of energetic-particle behavior in Spherical Tokamak Mou Maolin Supervisor : Z.T. Wang, C.J.Tang The Second A3 Foresight Workshop on Spherical.
Collisions and transport phenomena Collisions in partly and fully ionized plasmas Typical collision parameters Conductivity and transport coefficients.
XP NSTX Results Review Beam Modulation Effects on Ion Power Balance XP 737 P.W.Ross.
Excitation of ion temperature gradient and trapped electron modes in HL-2A tokamak The 3 th Annual Workshop on Fusion Simulation and Theory, Hefei, March.
CAE/GAE modes – link to electron transport in MAST? A.R. Field 1, R.J. Akers 1, L. Appel 1, D. Dunai 3, H. Smith 2, M. Turnyanskiy, M.Valovic 1, E. Verwichte.
HAGIS Code Lynton Appel … on behalf of Simon Pinches and the HAGIS users CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority.
SMK – ITPA1 Stanley M. Kaye Wayne Solomon PPPL, Princeton University ITPA Naka, Japan October 2007 Rotation & Momentum Confinement Studies in NSTX Supported.
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,
PLASMA HEATING AND HOT ION SUSTAINING IN MIRROR BASED HYBRIDS
1 ITPA St Petersburg April 2009G.Gorini JET results on the determination of thermal/non-thermal fusion yield from neutron emission spectroscopy.
ITER Standard H-mode, Hybrid and Steady State WDB Submissions R. Budny, C. Kessel PPPL ITPA Modeling Topical Working Group Session on ITER Simulations.
10 March 2009DVCM Corrections to the energy distribution of the NBI power PPF  Background  History of the problem  Proposed changes  Affected data.
Energy calibration at LHC J. Wenninger. Motivation In general there is not much interest for accurate knowledge of the momentum in hadron machines. 
Magnetic activity in protoplanetary discs Mark Wardle Macquarie University Sydney, Australia Catherine Braiding (Macquarie) Arieh Königl (Chicago) BP Pandey.
RF simulation at ASIPP Bojiang DING Institute of Plasma Physics, Chinese Academy of Sciences Workshop on ITER Simulation, Beijing, May 15-19, 2006 ASIPP.
2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.
RF codes for Transp Transp User Course 2014 Jim Conboy.
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Beam Species Measurements on the MAST NBI system Brendan Crowley Thanks to.
SLM 2/29/2000 WAH 13 Mar NBI Driven Neoclassical Effects W. A. Houlberg ORNL K.C. Shaing, J.D. Callen U. Wis-Madison NSTX Meeting 25 March 2002.
1Peter de Vries – ITBs and Rotational Shear – 18 February 2010 – Oxford Plasma Theory Group P.C. de Vries JET-EFDA Culham Science Centre Abingdon OX14.
Transport in three-dimensional magnetic field: examples from JT-60U and LHD Katsumi Ida and LHD experiment group and JT-60 group 14th IEA-RFP Workshop.
Objectives Much better spatial resolution Velocity space discrimination W. Heidbrink, M. Van Zeeland, J. Yu FIDA Imaging Proposal.
Physics of fusion power Lecture 12: Diagnostics / heating.
Radial Electric Field Formation by Charge Exchange Reaction at Boundary of Fusion Device* K.C. Lee U.C. Davis *submitted to Physics of Plasmas.
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority ITB formation and evolution with co- and counter NBI A. R. Field, R. J. Akers,
Improved performance in long-pulse ELMy H-mode plasmas with internal transport barrier in JT-60U N. Oyama, A. Isayama, T. Suzuki, Y. Koide, H. Takenaga,
1 Feature of Energy Transport in NSTX plasma Siye Ding under instruction of Stanley Kaye 05/04/09.
Simulations of NBI-driven Global Alfven Eigenmodes in NSTX E. V. Belova, N. N. Gorelenkov, C. Z. Cheng (PPPL) NSTX Results Forum, PPPL July 2006 Motivation:
A.Yu. Chirkov1), S.V. Ryzhkov1), P.A. Bagryansky2), A.V. Anikeev2)
1 Peter de Vries – ITPA T meeting Culham – March 2010 P.C. de Vries 1,2, T.W. Versloot 1, A. Salmi 3, M-D. Hua 4, D.H. Howell 2, C. Giroud 2, V. Parail.
NSTX Meeting name – abbreviated presentation title, abbreviated author name (??/??/20??) Goals of NSTX Advanced Scenario and Control TSG Study, implement,
53rd Annual Meeting of the Division of Plasma Physics, November , 2011, Salt Lake City, Utah When the total flow will move approximately along the.
Simulation of Turbulence in FTU M. Romanelli, M De Benedetti, A Thyagaraja* *UKAEA, Culham Sciance Centre, UK Associazione.
Plan V. Rozhansky, E. Kaveeva St.Petersburg State Polytechnical University, , Polytechnicheskaya 29, St.Petersburg, Russia Poloidal and Toroidal.
Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod S. D. Scott Princeton Plasma Physics Laboratory In collaboration with R. Granetz, D. Beals, C.
TH/7-1Multi-phase Simulation of Alfvén Eigenmodes and Fast Ion Distribution Flattening in DIII-D Experiment Y. Todo (NIFS, SOKENDAI) M. A. Van Zeeland.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
Saturn Magnetosphere Plasma Model J. Yoshii, D. Shemansky, X. Liu SET-PSSD 06/26/11.
Fast Ion Transport Options in TRANSP Presented at Energetic Particle SFG Meeting, PPPL June – D. McCune.
Particle in uniform B-field
Neoclassical Predictions of ‘Electron Root’ Plasmas at HSX
Conceptual Study for the Dynamic Control of Fusion Power Plant
15TH WORKSHOP ON MHD STABILITY CONTROL
Generation of Toroidal Rotation by Gas Puffing
Magnetic reconnection
First Experiments Testing the Working Hypothesis in HSX:
Investigation of triggering mechanisms for internal transport barriers in Alcator C-Mod K. Zhurovich C. Fiore, D. Ernst, P. Bonoli, M. Greenwald, A. Hubbard,
Comparisons of Measurements and Gyro-kinetic Simulations of Turbulence and Trans-port in Alcator C-Mod EDA H-Mode Discharges M. B. Sampsell, R. V. Bravenec.
T. Morisaki1,3 and the LHD Experiment Group
K. Ida1,2, R. Sakamoto1,2, M. Yoshinuma1,2, K. Yamasaki3, T
LECTURE II: ELEMENTARY PROCESSES IN IONIZED GASES
T. Morisaki1,3 and the LHD Experiment Group
2. Crosschecking computer codes for AWAKE
H. Nakano1,3, S. Murakami5, K. Ida1,3, M. Yoshinuma1,3, S. Ohdachi1,3,
D. V. Rose, T. C. Genoni, and D. R. Welch Mission Research Corp.
C.Mazzotta Peaked Density Profiles due to Neon Injection on FTU
Presentation transcript:

Clive Challis With thanks to: Doug McCune and Yuriy Baranov TRANSP NBCD bug Clive Challis With thanks to: Doug McCune and Yuriy Baranov Clive Challis - TRANSP User Group Meeting - 21 May 2004

Clive Challis - TRANSP User Group Meeting - 21 May 2004 Fast Ion Current ionisation Beam current driven by tangentially injected fast ions Fast ions that can circulate toroidally provide a current which depends on: Beam energy Number of fast ions Toroidal velocity component Fast ion slowing-down time Fast ions can be trapped in B field gradient if v||/v too small Trapped if |v||/v|<(2)0.5 (approx – Wesson, =r/R) Trapped ions do not drive current beam neutrals plasma fast ions Clive Challis - TRANSP User Group Meeting - 21 May 2004

Back Electron or Shielding Current Thermal electrons dragged by collisions with fast ions Bulk electron rotation given by momentum balance with fast and thermal ions For: Zbeam=Zplasma; Mbeam=Mplasma ve>>vi R>>r (no particle trapping) Momentum balance gives: nfast(v||fast-<ve>)-nion<ve>=0 Jnet=nfastev||fast-nee<ve> ne=nion+nfast  Jnet=0 thermal ions (nion) thermal electrons (ne, <ve>) fast ions (nfast, v||fast) Clive Challis - TRANSP User Group Meeting - 21 May 2004

Clive Challis - TRANSP User Group Meeting - 21 May 2004 Net Current Thermal electrons can be trapped in B field gradient if v||/v too small Trapped electrons do not carry current Trapped electrons drag on rotating thermal electron Shielding current reduced by factor 1.0-1.460.5 (approx – Wesson) electron-ion coulomb cross-section scales like Z2ion, so higher Z ions preferentially drag on electrons to prevent complete cancellation of fast ion current Resulting net current scales roughly as: Jnet~Jfast{1.0-(Zfast/Zeff)(1.0-1.460.5)} For Zbeam=1, high Zeff and/or large  advantageous Clive Challis - TRANSP User Group Meeting - 21 May 2004

Clive Challis - TRANSP User Group Meeting - 21 May 2004 TRANSP NBCD Bug TRANSP Zfast used to calculate the shielding current was accidentally reset by mixed H & He beams, or non-NBI fast ion calculations (e.g. fusion products, including He) When alpha-simulations were switched on (typical for JET, but not for MAST) the beam driven current was miscalculated using Zfast=2 rather than 1 to give: Jnet~Jfast{1.0-(2/Zeff)(1.0-1.460.5)} This reduces the current significantly in the core of low Zeff plasmas, but the effect diminishes at large  On-axis current drive vanishes for Zeff2, and the current profile becomes hollow (normally peaked for JET) Clive Challis - TRANSP User Group Meeting - 21 May 2004

Clive Challis - TRANSP User Group Meeting - 21 May 2004 Typical Case In this typical JET ITB plasma the TRANSP neutral beam driven current profiles are compared with and without the bug at different times Better agreement with PENCIL is achieved without the bug The corrected TRANSP calculation is better than PENCIL due to superior physics model In this case the bug resulted in a 40% reduction in total beam driven current Clive Challis - TRANSP User Group Meeting - 21 May 2004

Clive Challis - TRANSP User Group Meeting - 21 May 2004 History and Checks Doug McCune, who promptly located the bug from my symptoms, has determined the history of the bug: Introduced 18 March 2002 approx (30 May 2002 at JET - Jim) Removed 19 April 2004 approx For 2004 runs the absence of the bug can be confirmed by the presence of the following signals in the multiplot JBFACS: JBFAC,JBFACZ1,JBFACZ2 (as opposed to JBFAC,JBFAC0,JBFACNC with the bug) Alternatively, the shielding current calculation can be checked directly: JBFAC(=0)=1.0-Zbeam/Zeff (Zbeam=2 for H, D or T beams being the fault condition) Clive Challis - TRANSP User Group Meeting - 21 May 2004