Extension of High-Beta Plasma Operation to Low Collisional Regime

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Transcription:

EX/4-4 Extension of High-Beta Plasma Operation to Low Collisional Regime Satoru Sakakibara On behalf of LHD Experiment Group National Institute for Fusion Science SOKENDAI (The Graduate University for Advanced Studies)

Outline - Background and purpose of this study - Experimental Setup - High-beta experiments - Global properties of high-beta operations in low-collisional regime - Characteristics of high-beta discharges - Summary - Multi-pellet operations - Quasi-steady state operations with improvement of particle confinement 2/19

Strategy of high beta experiments <b> of 5.1 % was achieved in previous experiments verify an ability in high beta plasma production in currentless plasmas Extension of database of non-dimensional parameters (b, S, n*, r*) Physics Studies Stability, Plasma confinement in ergodic regime, magnetic island dynamics, transport caused by turbulence etc. high T and high b plasma is required Goal: <b> ~ 4 % at 1T (Final goal of LHD: 5 % at 1T) 3/19

Large Helical Device (LHD) Experiments have been done since 1998 All coils are superconductive. 10 pairs of RMP coils Specification: R = 3.5 ~ 4.1 m, a ~ 0.65 m Maximum B t ~ 3 T Heating Power: N-NBI 15 MW P-NBI (perp.) 10 MW ICRF ECH < 3 MW ~ 2 MW 4/19

R ax is a key parameter for high-beta R v ax (Magnetic axis in vacuum) is important for optimizing characteristics of MHD, transport and heating. Inward R ax outward Stability: Equilibrium: Transport: Heating: Confinement: hill weak dependence Increment of helical ripple Prompt loss of NB well (Experiment) Shafranov shift Shift Shafranov shift deteriorates transport and heating efficiency, although it is valid for stability R ax v (m) 5/19

R ax v scan experiments for high-beta - R ax v scan experiments were done in condition with constant heating power and electron density - Core instabilities were excited in the configuration with R ax v < 3.55 m R ax v of 3.56 m was selected R ax v scan with n e constant Optimum R ax v for pellet and gas-puff Unstable B t = -1 T B t = -1 T 6/19

<b> of 4.1% was successfully achieved High beta operation has been extended to low collisional regime Multi-pellet injections (Maximum beta) 4.1 %(T e0 = 0.9 kev, n e0 = 6 10 19 m -3 ) Gas puff (Quasi-steady state) 3.4 %(T e0 = 1.2 kev, n e0 = 3 10 19 m -3 ) R ax v = 3.56 m, B t = -1T, A p = 5.8 7/19

Low-n instabilities are suppressed with the increase in S Increase in S suppresses the amplitude of low-n mode The amplitude of low-n modes depend on the beta and magnetic Reynolds number, S, which is consistent with prediction of linear theory. Results of low-n* (high-s) experiments emphasize the obtained knowledge. Previous exp. Based on [Sakakibara PPCF2008] 8/19

Comparison between Pellet and Gas-puff Pellet discharge Gas-puff discharge Achieved <b> 4.1 % 3.4 % Duration time < 0.1 s > 0.5 s (limited by heating) T e0 0.9 kev (0.2 kev at B t = 0.425 T) 1.2 kev (< 0.5 kev at B t = 0.425 T) n e0 6 10 19 m -3 3 10 19 m -3 R axv = 3.56 m, B t = -1T, A p = 5.8 P Profile Peaked profile Broaden profile R ax shift ~0.44 m ~ 0.29 m Improvement of particle confinement Unclear (short duration) Clear Stability Core instability Edge instability subjects Long time duration Stability control Fueling to core 9/19

High-beta discharge with pellet injections Pellets were injected in NB and ICRF plasma Peaked n e and T e profiles were formed Central beta ~ 7% Shafranov shift DR : ~ 0.44 m & ICRF 10/19

Appearance of Core MHD mode - Pellet Discharge - Peaking of pressure profile leads to destabilization of core mode no profile flattening Increase in beta can stabilize the mode by Shafranov shift? No significant edge instability Electron diamag. i/2p=0.5 i/2p=1.0 i/2p=1.5 i/2p=2.0 11/19

Quasi steady-state high beta discharge with more than 3% - Gas-puff - Transition phenomenon appears in quasi-steady state operation Strong fluctuation appears limits the increase in beta Density fluctuation correlates with magnetic one Transition 12/19

Particle flux to divertor reduces after the transition Ion saturation current and density reduce after the transition. Ha starts to decrease with IS current before transition. <b dia > H a 13/19

Changes of plasma profiles before and after transition Increment of edge density after the transition [Toi, FST2010] No change of core density Extension of confinement region Magnetic field structure is changed? n e T e 14/19

Confinement region is extended to the outward Long L c around i/2p=2 extension of confinement region New edge MHD instability is excited limits the increase in b NBI NBI+ICRF m/n=1/2 m/n=2/3 15/19

Radial structures of the modes measured with CO 2 interferometer Observed modes are localized near edge Transition NBI NBI+ICRF i/2p = 2.0 i/2p = 1.5 m/n = 1/2 m/n= 2/3 16/19

Change of dominant mode with beta Resonance of the dominant mode : i/2p=3/2 2/1 Extension of confinement region leads to appearance of new resonant surface. - Dominant MHD mode is changed from inner region to outer one when m/n=2/3 b is increased. [A.Komori, POP2004] dominant ~ 3% ~ 3.4% m/n=2/3 NBI NBI+ICRF NBI NBI+ICRF dominant No excitation m/n=1/2 17/19

Discussion on Improvement of particle confinement Experimental observation - The transition with the spontaneous increase in <b> is found in high-beta regime, which is caused by the increase in peripheral electron density - After the transition, particle flux to divertor plate is obviously reduced - Plasma boundary is shifted to the outward (Thomson scattering) - Edge MHD instabilities are abruptly excited Speculations - Extension of plasma boundary magnetic field structure with short-lc is changed to that with long-lc (HINT2 calculation) confinement region is extended good particle confinement - Excitation of Edge MHD instabilities Appearance of new rational surface due to extension of long-lc region Change of magnetic topology is a key (n*, b, configuration etc.) [S.Sakakibara NF2013, PPCF2013] 18/19

Summary High-beta experiments have been done in order to extend operation regime to low collisional one. Volume-averaged beta value of 4.1 % was achieved at 1 T by multi-pellet injections, and 3.4 % could be maintained for a long time by gas-puff fueling. Strong instability excited in the core was observed in multi-pellet discharges, which is expected to be stabilized by magnetic well formation due to the increase in beta. Maximum beta in steady-state discharge (gas-puff) is realized by improvement of particle confinement. The reduction of particle flux to divertor is obviously observed after the transition. Edge MHD instabilities excited after the transition limit the achieved beta. 19/19

Reference Materials

MHD Equilibrium in Pellet discharge HINT2 predicts extension of stochastic regime Pressure profile Plasma is confined in stochastic regime i/2p Magnetic field structure Disturbance of magnetic field line 21

A p = 6.6 and 5.8(R ax = 3.56m, 1T) - Comparison of discharges - Beta value before transition is almost the same in both cases - The transition is observed only in A p = 5.8 Shafranov shift in A p = 6.6 is smaller than that in A p = 5.8 22

No transition and strong instabilities in core and edge at A p = 6.6 Excited modes are quite different despite b and P-profile are almost the same A p = 6.6 : core and edge instabilities are unstable R ax = 3.56 m configuration is not suitable for high-beta plasma production A p = 6.6 A p = 5.8 <b> Freq. i/2p=0.5 i/2p=1.0 i/2p=1.5 i/2p=2.0 23

A p = 6.6 and 5.8(R ax = 3.56m, 1T) - MHD Equilibrium - P 0 and pressure profile are almost the same A p = 6.6: i a /2p ~ 2, A p = 5.8: i a /2p ~ 3 A p = 6.6 and 5.8 (before and after transition) A p = 6.6 A p = 5.8 A p = 6.6 Before transition After transition 24

Fluctuation at divertor synchronizes with MHD mode Fluctuation of ion saturation current is enhanced during the transition Strong correlation with m/n = 2/3 MHD mode Fluctuation of ion saturation current m/n=2/3 Magnetic Fluctuation 25

Shielding by magnetic island? Increment of density is observed only in periphery Magnetic island appears around i/2p=1 surface after the transition suppress influx of particles to core? Before trans. Magnetic island? After trans. 26

MHD equilibria before and after transition m/n=1/2 m/n=2/3 27

Change of MHD activities with b Suppression of i/2p < 1 modes b b Suppression of i/2p 1 modes b Suppression of i/2p 2 modes <b dia >, n e i/2p = 1/2 i/2p = 1 i/2p = 3/2 i/2p = 2 i/2p = 5/2 28

Magnetic Configuration for high-beta Magnetic configuration was decided based on R ax v scan experiments with constant P NBI and n e. - A p = 6.6 in previous high-n* exp. - A p = 5.8 in recent low-n* exp. 3.56 m <b dia > (%) 4 3 2 1 0 A p = 5.8 P NBI, n e ~ constant 3.54 3.55 3.56 3.57 3.58 R ax (m) Pellet Gas-puff Previous High-b Recent High-b 29

Global Energy Confinement property Inward shift of R ax v recovers confinement property (A p = 5.8) - A p = 5.8: Improvement of particle confinement is one of reasons for recovery of global energy confinement property - A p = 6.6: The confinement property is almost the same (No improvement of particle confinement, strong instabilities ) A p = 6.6 (Prev. high-b) A p = 5.8 (Recent high-b) 30

Negative electric field is formed after the transition Profile of electric field is clearly changed after the transition - E r is significantly changed at R > 4.4 m Preliminary 31

Change of dominant mode with beta Excitation of edge MHD mode(m/n = 1/2, 2/3) just after the transition Extension of confinement region leads to appearance of new resonant surface. - Resonance of dominant mode is changed from inner region to outer one [A.Komori et al., POP2004] ~ 3% ~ 3.4% NBI NBI+ICRF NBI NBI+ICRF 32

Change of dominant mode with beta Resonance of the dominant mode : i/2p=3/2 2/1 - Consistent with extension of plasma confinement region Ion saturation current m/n = 2/3 mode ~ 3% m/n=2/3 ~ 3.4% m/n=1/2 No excitation 33

Strategy of high-beta Experiments in LHD High beta operation has been realized by two scenarios Standard scenario (broaden P-profile) - High A p configuration for optimizing heating efficiency, transport and MHD - <b> of 5.1 % was obtained at low-field Super Dense Core scenario (peaked P-profile) - Peaked P profile by multi-pellet injections - High density (> 10 20 m -3 ) - Central b of 10 % was realized at high-field Standard Scenario A p = 6.6 (2005~) A p = 6.3 (2004) A p = 5.8 (~2003) SDC Scenario - Steady-state high-beta discharge was realized in optimized configuration Verification of ability in high beta plasma production in heliotron 34