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Overview of Versatile Experiment Spherical Torus (VEST) Overview of Versatile Experiment Spherical Torus (VEST) Y.S. Hwang and VEST team March 29, 2017 CARFRE and CATS Dept. of Nuclear Engineering Seoul National University 23rd IAEA Technical MeetingExperimental on Researchresults and plans of Using VEST Small Fusion Devices, Santiago, Chille Outline Versatile Experiment Spherical Torus (VEST) . Device and discharge status Start-up experiments . Low loop voltage start-up using trapped particle configuration . EC/EBW heating for pre-ionization . DC helicity injection Studies for Advanced Tokamak . Research directions for high-beta and high-bootstrap STs . Preparation of long-pulse ohmic discharges . Preparation for heating and current drive systems . Preparation of profile diagnostics Long-term Research Plans Summary 1/36 VEST device and Machine status VEST device and Machine status 2/36 VEST (Versatile Experiment Spherical Torus) Objectives . Basic research on a compact, high- ST (Spherical Torus) with elongated chamber in partial solenoid configuration . Study on innovative start-up, non-inductive H&CD, high and innovative divertor concept, etc Specifications Present Future Toroidal B Field [T] 0.1 0.3 Major Radius [m] 0.45 0.4 Minor Radius [m] 0.33 0.3 Aspect Ratio >1.36 >1.33 Plasma Current [kA] ~100 kA 300 Elongation ~1.6 ~2 Safety factor, qa ~6 ~5 3/36 History of VEST Discharges • #2946: First plasma (Jan. 2013) • #10508: Hydrogen glow discharge cleaning (Nov. 2014) Ip of ~70 kA with duration of ~10 ms • #14945: Boronization with He GDC (Mar. 2016) Maximum Ip of ~100 kA • # ??: Long pulse with coil power supply upgrade (March. 2017) 4/36 Discharge Status (Shot #14945) VEST Discharge Status : 100kA with Boronization (#14945) • EC-assisted OH discharge – Plasma current 100 kA – Hydrogen plasma with Boronization – Tungsten & Graphite (inboard) limiter • Equilibrium parameters – R=0.45m/a=0.33m (A=1.36) – Elongation: 1.6 – 2.0 – Edge safety factor: ~ 7 • Limited discharge length – Fast ramp-up Require large Bv in the beginning – Wall eddy current Limited time response of Bv – Excessive vertical field near current peak early termination 5/36 Start-up Experiments Start-up Experiments 6/36 Start-up experiments Widely used Field Null Configuration (Breakdown/avalanche) The field null configuration has been generally used even for the ECH-assisted start-up of tokamaks. Frascati Tokamak Upgrade KSTAR DIII-D [G. Granucci et al, Nucl. Fusion 51 (2011) 073042] [Y.S. Bae et al 2009 Nucl. Fusion 49 022001] [NUCLEAR FUSION, Vol. 31. No. 11 (1991)] . Field null formation to maximize connection length and consequently sufficient EtBt/Bp . Null quality : size, sustaining time and location loop voltage and pre-ionization . Notes: KSTAR: not much help with higher ECH power in the ECH-assisted start-up DIII-D: vertical field pre-bias helps ohmic start-up with ECH pre-ionization 7/36 Start-up experiments Trapped Particle Configuration (TPC) Y. An et al., Nucl. Fusion 57 016001 (2017) Field null Trapped particle Efficient and robust tokamak start-up demonstrated • Mirror like magnetic field configuration – Enhanced particle confinement – Inherently stable decay index structure – Wider operation range of ECH power, pressure and low Vloop 8/36 Start-up Experiment in VEST Robust and Reliable TPC Start-up Applied to KSTAR Successfully Earlier plasma colomn formation than field null . Feasibility study of TPC in KSTAR • Even though low mirror ratio than ST, achieving efficient start-up with TPC • 2nd harmonic delay of 20 ms and ECH plasma density of 4x1018 m-2 • Ip formation with low Et less than 0.2 V/m J. Lee, et al., Proc. IAEA-FEC 2016 EX/P4-14 Start-up Experiment in VEST H.Y. Lee Low Loop Voltage Start-up with different ECH Power at Low TF Field in TPC Earlier Ip initiation at low loop voltage with larger ECH power in double swing TPC start-up Smaller resistivity initiate higher initial current to form sufficient size of closed flux surface Threshold current for successful inductive start-up (reference for outer PF start-up) 10/36 EC / EBW pre-ionization VEST pre-ionization with LFS XB mode conversion ECR 1.2 Coil Geometry 1.5 X-mode_2kW X-mode_3kW 1.0 X-mode_4kW X-mode_6kW 0.8 ] n -3 UH 1 m n 17 0.6 R 10 [ e n 0.4 0.5 0.2 0.0 30 35 40 45 50 55 60 65 70 75 80 85 2.45GHz R [cm] 0 6kW CW Z (m) ECR ECH 24 X-mode_2kW 21 X-mode_3kW X-mode_4kW X-mode_6kW -0.5 18 15 [eV] e 12 T -1 9 6 3 -1.5 30 35 40 45 50 55 60 65 70 75 80 85 0 0.2 0.4 0.6 0.8 1 J.G. Jo R (m) R [cm] 11/36 Start-up experiments in VEST Pre-ionization with Low-Field-Side Launch EC/EBW Heating • LFS perpendicular injection of ECW 10 kW – Over-dense plasma (X-wave tunneling) – Parametric decay with mode conversion – High density with collisional heating near UHR J.G. Jo et al., Phys. Plasmas 24 012103 (2017) • TPC configuration for Pre-ionization – Higher density plasma with broad density profile – Different density profile with Bt strength Low TF (Bo ~ 0.5 kG) High TF (Bo ~ 1 kG) 12/36 DC Helicity Injection DC Helicity Injection Start-up 20 15 [kA] 400.4 ms 401 ms 402 ms 403 ms 10 5 toroidal I 0 -1.0 -0.8 -0.6 [kV] -0.4 inj -0.2 V 0.0 2.0 1.5 1.0 [kA] 0.5 inj I 0.0 8 Plasma field @ Z = 0, R= 0.089 6 4 Lower Gun Location [mT] z 2 B 0 • R = 0.25 m -6 Vacuum field @ Z = 0, R= 0.089 • Z = - 0.804 m -7 -8 [mT] Magnetic Field Structure z -9 B • Stacking ratio, G = 7 ~ 8 -10 400 402 404 406 408 410 412 414 416 • Multiplication, M = ~ 16 Time [ms] The Electron Gun for DC Helicity Injection • High current electron beam based on arc discharge w/ washer stacks • Low impurity A toroidal current of up to ~20 kA has been generated by the electron gun • Increased multiplication factor confirmed as current streams reconnect • Very dynamic states of current sheet observed The electron gun J.Y. Park 13/36 Preparation for Advanced Tokamak Studies Studies for Advanced Tokamak 14/36 Preparation for Advanced Tokamak Studies Scopes of Advanced Tokamak Studies in VEST Fusion reactor requires high beta (or Q) and high bootstrap current Simultaneously Alpha heating dominant (high Q) High Bootstrap current fraction (high fb) Centrally peaked pressure profile Hollow current density profile (low li) High power Current density profile control neutral beam heating Profile diagnostics Bootstrap/EBW/LHFW Confinement and Stability? 15/36 Preparation for Advanced Tokamak Studies Experimental Research Direction for VEST Advanced Tokamak Study Scenario Powerful Core Neutral Beam Injection (NBI) resembling alpha heating tackles simultaneous achievement of high beta and high bootstrap current High beta limit in spherical torus favors high beta operation + High bootstrap current fraction reversed shear configuration Spherical Torus with Reversed Shear (RS) may provide AT regime ! • Sufficient confinement from ITB formation by RS • Possible high beta even with low li in RS due to low aspect ratio High power NBI to center, forming RS in VEST! Advanced Tokamak Regime in VEST* * Estimated by 0-D system code Low toroidal field(0.1T) with high βN(~7)< βN,Menard(8.7) and Ip(0.08 MA). Fully non-inductive CD with 80% bootstrap fraction may be possible with ~500kW. High H factor(~1.2) needs to be attempted by forming ITB with MHD stability. 16/36 Preparation for Advanced Tokamak Studies S.M. Yang, C.Y. Lee and Yong-Su Na Simulations for the VEST Advanced Tokamak Scenario Total power loss is calculated using NUBEAM simulations in various conditions (퐈퐏 = ퟏퟎퟎ 퐤퐀) 19 −3 Total loss ( ne0 = 2 ∗ 10 푚 ) 푬풃풆풂풎 R = 35 cm R = 40 cm 10푘푒푉 27% 33% 20푘푒푉 43% 70% 푃푒, 푃푖 at 15° injection 1.4 Pe-20keV,600kW 1.2 Pe-10keV,150kW 1.0 Pi-20keV,600kW 0.8 Pi-10keV,150kW (n = 2 ∗ 1019 푚−3) 0.6 e0 0.4 0.2 Heating power( 0.0 0.0 0.2 0.4 0.6 0.8 1.0 푟/푎 • Based on the result, R = 35 cm equilibrium is chosen for better NBI power absorption. • 15 degree of the injection angle is chosen considering both power loss and engineering issue in VEST and its heating power profiles are calculated. 17/36 Preparation for Advanced Tokamak Studies S.M. Yang, C.Y. Lee and Yong-Su Na Simulations for the VEST Advanced Tokamak Scenario 1-D transport simulation NBI heating with NUBEAM code (Density and equilibriums are given) 1D integrated modelling with ASTRA code with TGLF module (Density profile is given) L-mode (edge at r=0.9) and H-mode cases are compared 0-D system code analysis Low toroidal field 0.1 T High beta N 7 Plasma current 80 kA Non-inductive 100% Bootstrap fraction 80% Required NB power 500 kW 18/36 Preparation for Advanced Tokamak Studies Preparation for Long Pulse Ohmic Discharges TF with Ultra Capacitor from Battery PF in H-bridge circuit with Extra Capacitors S.C. Hong and J.Y. Park 19/36 Preparation for Advanced Tokamak Studies J.H. Yang and S.C. Kim Development of Long Pulse Ohmic Discharges +10ms +20ms +30ms -10ms 0ms CE = 0.4 20/36 With great help from Dr. S.H. Hong (NFRI) Preparation for Advanced Tokamak Studies Discharge Improvement with Boronization • Boronization during Helium Glow discharge cleaning – Carborane (C2B10H12) is used for non-toxic boronization – Water concentration recovery slowed down (RGA) • Oxygen atom line emission (777.0 nm) reduced by 3 fold – High density expected: More prefill gas (Hα line emission) Helium flow (MFC 2.0 sccm) Caborane oven (baked 50°C) Diaphragm valve Top flange (CF 6 inch) 21/36 Preparation for Advanced Tokamak Studies Diagnostics, Heating and Current Drive Systems in VEST Profile Diagnostic Systems Heating and Current Drive Systems Magnetics and Spectroscopy Neutral Beam Injection System with ~500kW at 15keV from KAERI Interferometer Interferometry with 94GHz, multi-channel from SNU/UNIST Low Hybrid Fast Wave H/CD with ~20kW at 500MHz from KAERI/KAPRA/KWU Thomson Scattering with NdYAG laser Electron Cyclotron/Bernstein from SNU/NFRI/JNU/SogangU Wave H/CD with ~30kW at 2.45GHz ECH from SNU/KAPRA 22/36 High power central heating High Power NBI System : Dual Beam to Single Beam S.H.
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