Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.

Slides:



Advertisements
Similar presentations
Glenn Bateman Lehigh University Physics Department
Advertisements

Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
17. April 2015 Mitglied der Helmholtz-Gemeinschaft Application of a multiscale transport model for magnetized plasmas in cylindrical configuration Workshop.
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.
SUGGESTED DIII-D RESEARCH FOCUS ON PEDESTAL/BOUNDARY PHYSICS Bill Stacey Georgia Tech Presented at DIII-D Planning Meeting
Nonlinear Simulations of ELMs with NIMROD D.P. Brennan Massachussetts Institute of Technology Cambridge, MA S.E. Kruger Tech-X Corp, Boulder, CO A. Pankin,
Discussion on application of current hole towards reactor T.Ozeki (JAERI) Current hole plasmas were observed in the large tokamaks of JT-60U and JET. This.
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.
Physics Analysis for Equilibrium, Stability, and Divertors ARIES Power Plant Studies Charles Kessel, PPPL DOE Peer Review, UCSD August 17, 2000.
Proposals for Next Year’s MFE Activities C. Kessel, PPPL ARIES Project Meeting, Sept. 24, 2000.
Energy loss for grassy ELMs and effects of plasma rotation on the ELM characteristics in JT-60U N. Oyama 1), Y. Sakamoto 1), M. Takechi 1), A. Isayama.
11 th European Fusion Physics Conference, Aix-en-Provence, France, Samuli Saarelma, Edge stability in tokamak plasmas Edge stability in tokamak.
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.
H. Urano, H. Takenaga, T. Fujita, Y. Kamada, K. Kamiya, Y. Koide, N. Oyama, M. Yoshida and the JT-60 Team Japan Atomic Energy Agency JT-60U Tokamak: p.
SIMULATION OF A HIGH-  DISRUPTION IN DIII-D SHOT #87009 S. E. Kruger and D. D. Schnack Science Applications International Corp. San Diego, CA USA.
6 th Japan-Korea Workshop on Theory and Simulation of Magnetic Fusion Plasmas Hyunsun Han, G. Park, Sumin Yi, and J.Y. Kim 3D MHD SIMULATIONS.
Kinetic Effects on the Linear and Nonlinear Stability Properties of Field- Reversed Configurations E. V. Belova PPPL 2003 APS DPP Meeting, October 2003.
Simulation Study on behaviors of a detachment front in a divertor plasma: roles of the cross-field transport Makoto Nakamura Prof. Y. Ogawa, S. Togo, M.
1 Integrated Simulation Code for Burning Plasma Analysis T.Ozeki, N.Aiba, N.Hayashi, T.Takizuka, M.Sugihara 2, N.Oyama JAERI 、 ITER-IT 2 IEA Large Tokamak.
Japanese Efforts on the Integrated Modeling - Part II : JAEA Contribution - T. Takizuka (JAEA) acknowledgments : T. Ozeki, N. Hayashi, N. Aiba, K. Shimizu,
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
O. Sauter Effects of plasma shaping on MHD and electron heat conductivity; impact on alpha electron heating O. Sauter for the TCV team Ecole Polytechnique.
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.
Discussions and Summary for Session 1 ‘Transport and Confinement in Burning Plasmas’ Yukitoshi MIURA JAERI Naka IEA Large Tokamak Workshop (W60) Burning.
第16回 若手科学者によるプラズマ研究会 JAEA
ITER Standard H-mode, Hybrid and Steady State WDB Submissions R. Budny, C. Kessel PPPL ITPA Modeling Topical Working Group Session on ITER Simulations.
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.
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
Nonlinear interactions between micro-turbulence and macro-scale MHD A. Ishizawa, N. Nakajima, M. Okamoto, J. Ramos* National Institute for Fusion Science.
Comparison of Ion Thermal Transport From GLF23 and Weiland Models Under ITER Conditions A. H. Kritz 1 Christopher M. Wolfe 1 F. Halpern 1, G. Bateman 1,
Planned Theory Contributions to the FY’2011 Joint Research Target on Pedestal Research R. J. Hawryluk Thanks to the Pedestal Working Group: C-S Chang,
D. Tskhakaya et al. 1 (13) PSI 18, Toledo July 2008 Kinetic simulations of the parallel transport in the JET Scrape-off Layer D. Tskhakaya, R.
Contribution of KIT to LHD Topics from collaboration research on MHD phenomena in LHD S. Masamune, K.Y. Watanabe 1), S. Sakakibara 1), Y. Takemura, KIT.
1 Lawrence Livermore National Laboratory Influence of Equilibrium Shear Flow on Peeling-Ballooning Instability and ELM Crash Pengwei Xi 1,2, Xueqiao Xu.
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
Radial Electric Field Formation by Charge Exchange Reaction at Boundary of Fusion Device* K.C. Lee U.C. Davis *submitted to Physics of Plasmas.
4th Transport/ITB IPTA Meeting, St Petersburg, 8-12 April Role of Edge Current in ELM Behaviour: Modelling of Recent Current Ramp Experiment in.
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,
QAS Design of the DEMO Reactor
MCZ Active MHD Control Needs in Helical Configurations M.C. Zarnstorff 1 Presented by E. Fredrickson 1 With thanks to A. Weller 2, J. Geiger 2,
1 Feature of Energy Transport in NSTX plasma Siye Ding under instruction of Stanley Kaye 05/04/09.
1 SIMULATION OF ANOMALOUS PINCH EFFECT ON IMPURITY ACCUMULATION IN ITER.
Role of thermal instabilities and anomalous transport in the density limit M.Z.Tokar, F.A.Kelly, Y.Liang, X.Loozen Institut für Plasmaphysik, Forschungszentrum.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
ZHENG Guo-yao, FENG Kai-ming, SHENG Guang-zhao 1) Southwestern Institute of Physics, Chengdu Simulation of plasma parameters for HCSB-DEMO by 1.5D plasma.
ELM propagation and fluctuations characteristics in H- and L-mode SOL plasmas on JT-60U Nobuyuki Asakura 1) N.Ohno 2), H.Kawashima 1), H.Miyoshi 3), G.Matsunaga.
Fast response of the divertor plasma and PWI at ELMs in JT-60U 1. Temporal evolutions of electron temperature, density and carbon flux at ELMs (outer divertor)
DIII-D RMP simulations: enhanced density transport and rotation screening V.A. Izzo, I. Joseph NIMROD meeting:
1 ASIPP Sawtooth Stabilization by Barely Trapped Energetic Electrons Produced by ECRH Zhou Deng, Wang Shaojie, Zhang Cheng Institute of Plasma Physics,
Pedestal Characterization and Stability of Small-ELM Regimes in NSTX* A. Sontag 1, J. Canik 1, R. Maingi 1, J. Manickam 2, P. Snyder 3, R. Bell 2, S. Gerhardt.
Plan V. Rozhansky, E. Kaveeva St.Petersburg State Polytechnical University, , Polytechnicheskaya 29, St.Petersburg, Russia Poloidal and Toroidal.
G. Matsunaga 1), M. Okabayashi 2), N. Aiba 1), J. A. Boedo 3), J. R. Ferron 4), J. M. Hanson 5), G. Z. Hao 6), W. W. Heidbrink 7), C. T. Holcomb 8), Y.
1 V.A. Soukhanovskii/IAEA-FEC/Oct Developing Physics Basis for the Radiative Snowflake Divertor at DIII-D by V.A. Soukhanovskii 1, with S.L. Allen.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA Influence of ion orbit width on threshold of neoclassical tearing modes Huishan Cai 1, Ding Li 2, Jintao.
Mechanisms for losses during Edge Localised modes (ELMs)
Finite difference code for 3D edge modelling
Center for Plasma Edge Simulation
Reduction of ELM energy loss by pellet injection for ELM pacing
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.
Investigation of triggering mechanisms for internal transport barriers in Alcator C-Mod K. Zhurovich C. Fiore, D. Ernst, P. Bonoli, M. Greenwald, A. Hubbard,
More on Pedestal and ELMs
T. Morisaki1,3 and the LHD Experiment Group
Non-Local Effects on Pedestal Kinetic Ballooning Mode Stability
New Results for Plasma and Coil Configuration Studies
20th IAEA Fusion Energy Conference,
H. Nakano1,3, S. Murakami5, K. Ida1,3, M. Yoshinuma1,3, S. Ohdachi1,3,
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2

Introduction Energy loss caused by edge localized modes (ELMs) is crucial for reducing the divertor plate lifetime and limiting the plasma confinement in tokamaks. It is necessary to clarify the physical mechanism of collisionality dependence of the ELM energy loss. Purpose of this paper We develop an integrated simulation code TOPICS-IB based on a transport code with a stability code for the peeling-ballooning modes and a scrape-off-layer (SOL) plasma model. Collisionality dependence of the ELM energy loss is investigated by artificially enhancing the collisionality in models of bootstrap current and SOL plasma. ELM energy loss was found to decrease with increasing the collisionality in multi- machine experiments. Loarte, PPCF03

TOPICS-IB : TOPICS extended to Integrated simulation for Burning plasma 1.5D core transport code ( TOPICS ) 2D Grad-Shafranov equation 1D transport & current diffusion equations ELM model : Enhance transport 2D MHD equilibrium Eigenvalue & Eigenfunction Heat & particle flows across separatrix Boundary conditions at separatrix SOL transport model (Five-point model) Integral fluid equations Exponential radial profiles with characteristic scale length Flux-tube geometry Linear MHD stability code ( MARG2D ) Applicable to wide range of mode numbers from low to high Eigenvalue problem of 2D Newcomb equation (See details at TH/P8-1)

ELM model (Ozeki, FST06) Pedestal formation : Neoclassical transport in peripheral region and anomalous in inside region (given pedestal width Δ ped ) ELM enhanced transport is maintained for a given time-interval (δt ELM ). Stabilities of n=1-30 modes are examined by MARG2D (Tokuda, PoP99) in each time step along the pedestal growth. When modes become unstable, ELM enhanced diffusivities (χ ELM ) are added on the basis of radial profiles of eigenfunctions of unstable modes. (given maximum χ ELM max, N: total number of unstable modes)

SOL model (Hayashi, PSI06) Validated by particle code Validated by fluid codes Point model based on integral fluid equations easily reproduces many static features found in experiments. (Stangeby, textbook) Dynamic version of the point model (Five-point model) has been developed for the integrated ELM modeling. Parallel heat conduction and equipartition energy depend on the collisionality. Flux-tube geometry - 2 SOL & 2 divertor regions (5 positions) - Symmetry assumed in this paper

Integrated simulation result by TOPICS-IB

Transient behavior of core-pedestal-SOL-divertor plasmas along pedestal growth and ELM crash Simulation condition : JT-60U like parameters - R=3.4 m, a=0.9 m, I p =1.5 MA, B t =3.5 T, κ~1.5, δ~0.21, Z eff = , P NB =12 MW, β N =0.8-1 TOPICS-IB successfully simulates the transient behavior of whole plasma. - ELM duration δt ELM = 200 μs, diffusivity χ ELM max =100 m 2 /s Pedestal width Δ PED = Fixed density profile, n div =1x10 20 m -3 (High recycling divertor)

Increase of SOL temperature mitigates the radial edge gradient and lowers the ELM energy loss. Electron energy loss is larger than the ion one, due to larger heat conduction parallel to the magnetic field. Energy flows into the SOL and the SOL- divertor temperatures rapidly increases. The resultant energy loss (< 10% of W ped ) is comparable with that in JT-60U.

Reduction of ELM energy loss through bootstrap current

Bootstrap current decreases with increasing the collisionality and intensifies the magnetic shear at the pedestal region. Bootstrap current reduces the area and the edge value of ELM enhanced transport. The collisionality in the bootstrap current model is artificially enhanced by C BS =100 (enhanced collisionality: ν* ped = C BS ν* ped0 = 9). The increase of magnetic shear reduces the width of eignfunctions of unstable modes.

Total ELM energy loss is about 3 times larger than that in the case with SOL model. (Importance of SOL plasma) Simulation condition : T SOL =100 eV, SOL model is not used to clear only the bootstrap current effect. fixed B.C. w/o SOL model ELM energy loss is reduced by increasing collisionality in bootstrap current. Both electron and ion energy losses are reduced in almost the same ratio.

Reduction of ELM energy loss through SOL transport

SOL electron temperature increases with the collisionality, because the parallel heat conduction is inversely proportional to the collisionality. SOL electron temperature increases with collisionality, while ion one decreases. The collisionality in SOL model is artificially enhanced by C SOL =100 (ν* ped = 9). SOL ion temperature decreases with increasing the collisionality, because the equipartition energy flows is proportional to the collisionality.

ELM energy loss is reduced by increasing collisionality in SOL transport. Total ELM energy loss is reduced according to the electron energy loss and the ion contribution is small. For higher collisionality, the SOL electron temperature increases more and the electron energy loss is reduced. On the contrary, the SOL ion temperature decreases and the ion energy loss is enhanced a little.

Dependence of ELM energy loss on the collisionality and the model parameters

Bootstrap current and SOL transport have major effect on the collisionality dependence. Collisionality in both models is enhanced by C=C BS =C SOL. When the collisionality is enhanced by C=100, the electron energy loss is reduced by about 1/3, but the ion one is reduced a little. Total energy loss is reduced about half. Model parameter dependence Standard (C=1) : δt ELM =200 μs, χ ELM max =200 m 2 /s, Δ ped = 0.05 The magnitude of ELM energy loss is changed by the model parameters, but its collisionality dependence is unchanged. CaseStandardδt ELM x2χ ELM max x2Δ ped x2 & χ ELM max x4 ΔW ELM /W ped ΔW ELM /W ped ~0.05 was measured in JT-60U plasmas with ν* ped ~0.1.

Conclusion (1/2) - An integrated simulation code TOPICS-IB based on a 1.5D transport code with a stability code for peeling- ballooning modes and a SOL model has been developed to clarify self-consistent effects of ELMs and SOL on the plasma performance. - Experimentally observed collisionality dependence of the ELM energy loss is found to be caused by both the edge bootstrap current and the SOL transport. - Bootstrap current decreases with increasing the collisionality and intensifies the magnetic shear at the pedestal region. The increase of magnetic shear reduces the width of eigenfunctions of unstable modes, which results in the reduction of the area and the edge value near the separatrix of the ELM enhanced transport.

Conclusion (2/2) - When an ELM crash occurs, the energy flows into the SOL and the SOL temperature rapidly increases. The increase of SOL temperature lowers the ELM energy loss due to the flattening of the radial edge gradient. The parallel electron heat conduction determines how the SOL temperature increases. For higher collisionality, the conduction becomes lower and the SOL electron temperature increases more. - By the above two mechanisms, the ELM energy loss decreases with increasing the collisionality. The bootstrap current and the SOL transport have the major effect on the collisionality dependence.

Future work Effect of plasma shape Model validation - Different plasma shape affects the ELM energy loss through the change of the mode structure. - Comparison not only with experiments but also with nonlinear simulations - ΔW ELM /W ped 10 % in other machines Model improvement - Density dynamics (density collapse enhances ΔW ELM by about 40 % under assumption of similar collapse to temperature.) - Increase of bootstrap current near the separatrix changes the unstable model number from medium-n to low-n (n<10), but does not change the localization of eigenfunctions near the pedestal region.

Mode characteristics in the present simulation - When the collisionality in the bootstrap current model is enhanced by C BS =100, the pressure profile does not change very much at the ELM onset. Ballooning mode is dominant rather than the peeling mode. - Increase of bootstrap current near the separatrix changes the unstable model number from medium-n to low-n (n<10), but does not change the localization of eigenfunctions near the pedestal region.