Electric circuit analysis for plasma breakdown in JT-60SA

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J. Plasma Fusion Res. SERIES, ol. 9 (1) Electric circuit analysis for plasma breakdown in JT-6SA Kunihito YAAUCHI 1), Katsuhiro SHIADA 1), Tsunehisa TERAKADO 1), akoto ATSUKAWA 1), Philippe CARA ), Elena GAIO 3), aurizio SANTINELLI 3), Roberto COLETTI ) and Alberto COLETTI 5) 1) Japan Atomic Energy Agency, Naka, Ibaraki, Japan ) CEA, IRF, Cadarache, Saint-Paul-lez-Durance, France 3) Consorzio RFX, Euratom-ENEA Association, Padova, eneto, Italy ) ENEA, Frascati, Rome, Italy 5) Fusion for Energy, Garching, Bavaria, Germany (Received: 3 October 9 / Accepted: 13 February 1) To obtain stable plasma breakdown and for designing the details of a power supply system in JT-6SA, a precise evaluation of the magnetic field performance using an accurate circuit analysis model has to be conducted. This evaluation should include AC/DC converters such as thyristor converters and a high voltage generation circuit which consists of a DC current interrupter and a resistor set. In this paper, the preparation procedure of the analysis model is presented. Using this modeling method, a circuit analysis including not only complex interactions but also nonlinear phenomenon can be performed. As one of the applications of it, a circuit analysis of the tokamak system JT-6SA is demonstrated using the PSI code. Specifically, some circuit analysis results of plasma breakdown at t= 6 ms are shown using an ideal voltage source and a thyristor converter model for comparison. Then, the voltage fluctuations of the generator (H-G, A) at plasma initiation and their influence are also described. Keywords: JT-6SA, breakdown, circuit analysis, passive coil model, converter, generator, PSI 1. Introduction A high current of about 5 ka will be induced in the passive structures such as the vacuum vessel and the stabilizing plate at plasma initiation in JT-6SA [1], because the total electric resistance of the passive structures is approximately 16.5 and the breakdown electric field of.5 /m is expected for stable plasma initiation from the experiments of JT-6U []. Therefore, a precise evaluation of the magnetic field performance using an accurate circuit analysis model has to be possible, and must be conducted to obtain stable plasma breakdown and for designing the details of a power supply system. This evaluation should include AC/DC converters such as thyristor converters and a high voltage generation circuit which consists of a DC current interrupter and a resistor set. In this paper, the preparation procedure of the analysis model is presented. Using this modeling method, a circuit analysis including not only complex interactions but also nonlinear phenomenon can be performed. As one of the applications of it, a circuit analysis of the tokamak system JT-6SA is demonstrated using the PSI code. PSI is a simulation software designed for power electronics, motor control, and dynamic system simulation. (Powersim Inc.: http://www.powersimtech.com/) The purpose of the circuit analysis is to obtain stable plasma breakdown and for designing the details of a power supply system in JT-6SA. Specifically, some circuit analysis results of plasma breakdown at t= 6 ms are shown using an ideal voltage source and a thyristor converter model for comparison. The delay effect on the converter voltage control is summarized as the first achievement. The voltage fluctuations of the generator (H-G, A) at plasma initiation are also described, because large reactive power fluctuations may cause large voltage fluctuations and sudden phase shifts of the AC voltage supplied by H-G and consequently applied to the thyristor converters.. Configuration of JT-6SA Coil Power Supplies Figure 1 shows a schematic circuit diagram of the AC power system for Poloidal Field (PF) coils. In JT-6SA, there are ten superconducting PF coils, i.e. four Central Solenoids (CS) and six Equilibrium Field (EF) coils, and they are energized by the motor-generator (H-G) through AC/DC converters. H-G is reused from JT-6, and consists of a synchronous generator, a flywheel and an induction motor for driving. The main specification of H-G is shown in Table 1. There are two kinds of AC/DC converter for the PF coils. One is the low voltage author s e-mail: yamauchi.kunihito@jaea.go.jp 1 by The Japan Society of Plasma Science and Nuclear Fusion Research

K. Yamauchi et al., Electric Circuit Analysis for Plasma Breakdown in JT-6SA 75 k Power Grid 11 A 75 k/66 k 5 A 66 k/11 k H-G A.65 GJ G F W 18 k 15-15 Base PS 939/±1kA TG 3.1A units 18k/83.5 %Z: 3.1% at 77.6Hz Base PS 939/-1kA Base PS (PS-CS1) Base PS (PS-CS) Base PS (PS-CS3) Base PS (PS-CS) Base PS (PS-EF1) Booster PS (PSB-EF1) Base PS (PS-EF) Booster PS (PSB-EF) Base PS (PS-EF3) Poloidal Field Coil PSs Base PS (PS-EF) Base PS (PS-EF5) Booster PS (PSB-EF5) Base PS (PS-EF6) Booster PS (PSB-EF6) PNBI ( W) CrowBar Switch Booster PS ±5k/kA (forward) 7.5 Fig. 1 Schematic circuit diagram of AC power system for Poloidal Field (PF) coils. <.1 37.5 7.5 thyristor converter (±1 k, ± ka) with continuous rating, and is named as Base PS. Another is the high voltage thyristor converter (±5 k, / 1.5 ka) with short-time rating, and is reused from ertical field coil PS (PS) in JT-6. In JT-6SA, it is renamed as Booster PS (PSB). Though Base PS is used for all the PF coils, Booster PS is utilized for EF1,, 5 and 6 coils only. Figures and 3 show schematic DC circuit diagrams of the typical PF coil PSs with Booster PS and with Switching Network Unit (SNU), respectively. SNU is involved in the PF coil PSs without Booster PS, and is a high voltage generator ( 5 k) that consists of a DC current interrupter and a resistor set. Unlike Booster PS powered by H-G directly, SNU is workable with using the energy stored in the PF coil. Both Booster PS and SNU can be basically operated to obtain a high voltage for short duration of plasma breakdown and initiation. Therefore, the PF coils are driven by Base PSs for most of the operation period including the pre-magnetization and plasma current flat-top phases. Table 1 ain specification of H-G Rated capacity A Rated voltage Rated current Frequency Rotating speed Available discharge energy Drive type 3. Analysis odel 18 k 183 A 77.6 5. Hz 58 6.5 rpm 65 J Induction motor drive 3.1. odeling of PF Coils Since the PF coils are magnetically coupled with not only other PF coils but also many conductor elements such as the vacuum vessel and the stabilizing plate, their interactions should be included. Of course, the plasma is also coupled with them magnetically. But, it is not Quench Protection Circuit (Hybrid type) ±.k/±ka Current Reversing Link EF1 (Superconducting Coil) 37.5 Booster PS ±5k/-1.5kA (reverse) Fig. Schematic DC circuit diagram of EF1 coil PS Fig. 3 (Typical PF coil PS with PSB). -3 CrowBar Switch <.1 Quench Protection Circuit (Hybrid type) ±.k/±ka T3G 3.1A units 18k/83.5 %Z: 3.1% at 77.6Hz Base PS 939/±1kA units Current Reversing Link necessary to be considered at the plasma breakdown phase because there is no plasma. Assuming axial symmetry of tokamak device, the passive structures could be represented as an assembly of about 1 thin passive poloidal field coils in order to calculate their induced eddy current []. However, there CS1 (Superconducting Coil) O/C Switching Network Unit -5k Schematic DC circuit diagram of CS1 coil PS (Typical PF coil PS with SNU). R1 R 1

K. Yamauchi et al., Electric Circuit Analysis for Plasma Breakdown in JT-6SA 1 n I 1 I I n is no easily available circuit model applicable to such a multiple coil with magnetic coupling in the conventional circuit analysis code. In fact, a calculation of 13 mutually coupled coils (1 PF and 1 passive coils) can not be achieved using the built-in circuit elements in the conventional codes such as PSI (six coupled inductors at most) and PSCAD/ETDC (no such an element). In addition, although the number of the passive coils was chosen as 1 in this case from the experience considering the stability of numerical analysis and the viewpoint of shortening the calculation time, the model of the passive structures can be further divided into more passive coils for high precision. To solve this problem, we have utilized a very conventional and ideally flexible circuit element, i.e. externally controlled current source. Figure indicates the multiple coil circuit model based on the current source equivalent circuit. The process is as follows; (1) Observing the applied voltage at the terminals of coils () Deriving the supplied magnetic flux (= voltage-time product) into each coil by the numerical integration of the observed voltages (3) Providing the coil current value I to the externally controlled current source using the equation of = LI. Here, L is the inductance matrix. Practically the coil currents can be calculated by the following equation; I n 13 i 1 L 1 L L n Fig. ultiple coil circuit model based on current source ni dt i 13 i i _ prev I (1) n _ prev ni Δt i 1 where ni is the 13 13 susceptance matrix for the 1 PF and 1 passive coils, and I n_prev and i_prev are the current and voltage values at the previous time step, respectively. As for the 1 passive coils, the terminal voltage is calculated from the resultant current value and the resistance matrix, and is internally used to the current PSCAD is a power system simulation software for the design and verification of all types of power systems. ETDC is the simulation engine, which is now the integral part of PSCAD graphical user interface. (anitoba HDC Research Centre Inc.: https://pscad.com/) 1 n I 1 I I n equivalent circuit. atrix Operation calculation at the next time step. In the case of PSI, such a process was realized by several control blocks using C language. While, the similar technique is possible using Fortran in the case of PSCAD/ETDC. The developed model has the following merits; (a) Sensitivity study of the circuit parameter is easy. (b) Geometry of the passive structures can be quickly updated. (c) Expansion to more advanced model which can involve the plasma behavior such as position and shape could be possible. In this paper, the PF coils and the passive structures with magnetic coupling in JT-6SA are modeled. However, using this modeling method, a circuit analysis including not only complex interactions but also nonlinear phenomenon can be performed. 3.. odeling of Coil Power Supplies Figure 5 shows the DC circuit diagram of the PSI simulation model for a plasma breakdown analysis. In this analysis model, Base PSs with CrowBar circuit are bypassed for simplicity because Booster PSs and SNUs are working during plasma breakdown. Similarly, Quench Protection Circuits (QPCs) are also bypassed for simplicity since they works in the case of a superconducting coil quench or a PS apparatus failure. For modeling of SNUs, ideal switches are used as the DC circuit interrupters, and all of them open together at t= ms. The resistance value of each SNU is properly PSB-EF1 ±5k /-1.5kA PSB-EF ±5k /-1.5kA PSB-EF5 ±5k /-1.5kA PSB-EF6 ±5k /-1.5kA.5.5.5.5 8.6m 7.mH 1.55m 9 H 9.8m 15 H 8.6m 7.mH 1.57m 19 H 9.8m 15 H.679.315 1.55m 18 H 1.38m 38 H 1.35m 1 H 1.1m 171 H 8.6m 7.mH 1.51m 5 H 9.8m 15 H 1.m 19 H 1.1m 3 H 8.6m 7.mH 1.58m 5 H 9.8m 15 H CS1 CS CS3 CS EF1 EF EF3 EF EF5 EF6 11 13 Fig. 5 DC circuit diagram of PSI simulation model ICS1 ICS ICS3 ICS IEF1 IEF IEF3 IEF IEF5 IEF6 I11 I13 atrix Operation for plasma breakdown analysis. 1 PF Coils 1 Passive Coils

K. Yamauchi et al., Electric Circuit Analysis for Plasma Breakdown in JT-6SA selected by the used scenario. Booster PS consists of forward and reverse two-quadrant thyristor converters. To provide the smooth coil current zero crossing, a circulating current operation is utilized. Therefore, to reduce the ripples of the circulating current between the forward and reverse converters, DC reactors are attached to Booster PS. As for other circuit elements, some resistances and inductances, such as DC feeders of about m between the PF coils and their PS components, are considered. 3.3. odeling of AC Power System In JT-6SA, the thyristor converters for the PF coils are powered by H-G. Unlike the power grid system, the frequency varies momentarily because the rotating speed of H-G depends on the rotational kinetic energy stored in the rotor with the flywheel. Especially in plasma breakdown phase, large reactive power fluctuations may cause large voltage fluctuations and sudden phase shifts of the AC source voltage for the thyristor converters. Therefore, it is important to model H-G for realistic analysis. For modeling of H-G, the built-in circuit element of 3-phase synchronous machine with external excitation is applied. The H-G machine is accelerated to the rated maximum rotating speed before the operation start (t= ms), and then provides power by converting the rotational kinetic energy into electric energy. In addition, a mechanical load element is used to represent the flywheel effect of the H-G rotor and the total mechanical losses due to friction and windage that is assumed as the constant torque at the rated maximum rotating speed. To follow the momentarily varying frequency of H-G, a vector phase-locked loop (PLL) is modeled for synchronization. The output voltage of H-G is controlled by PI feedback regulation at 18 k with the external excitation circuit. Phase-shifting converter transformers ( 7.5, 7.5,.5 and 37.5 for Booster PSs) are used in order to suppress harmonics in the H-G power line. Therefore, they are also modeled using multiple built-in single-phase transformer elements. 3.. Control ethod For the control of Booster PS, a feedforward control system is applied for fast response. Figure 6 indicates the block diagram of the feedforward control for Booster PS. Coil oltage Coil Current Circulating Current vl(k1/) (Reference) il(k) (Readout) ic(k1) (Reference) ic(k) (Readout) Reverse ode Fwd. conv.: No current Rev. conv.: Load current Fwd. Conv. Current -1.5-1.81 ai (T=1 ms) (T=1 ms) (T=1 ms) (T=1 ms) Conv. Current [ka] 3.63 1.81-1.81 Load Current bi ci di 1.81 Rev. Conv. Current Converter Output oltage ei(k) Fig. 6 Block diagram of feedforward control for Booster PS. Forward ode Fwd. conv.: Load current Rev. conv.: No current Load Current [ka] 3.63 oltage [k] Current [ka] 3 1-1 EF6 (Thy. Conv.) EF6 (Ideal -source) Fwd. Conv. (EF6) Rev. Conv. (EF6) - -.1.1..3..5.6.7 Fig. 8 Current waveforms of EF6 coil and thyristor - - converters. EF6 Fwd. Firing Angle EF6 oltage (Thy. Conv.) EF6 oltage (Ideal -source) 1 1 1 8 6 Firing Angle [deg] -1.5-6 Circulating Current ode (Fwd.) Fwd. conv.: Load current Circ. current (1.81-kA const.) Circulating Current ode (Rev.) Rev. conv.: Circ. current (1.81-kA const.) Fwd. conv.: Circ. current (1.81-kA const.) Rev. conv.: Load current Circ. current (1.81-kA const.) Fig. 7 Diagram of circulating current control mode for Booster PS. -8 -.1.1..3..5.6.7 Fig. 9 Waveforms of EF6 coil voltage and firing angle for thyristor converters. 3

K. Yamauchi et al., Electric Circuit Analysis for Plasma Breakdown in JT-6SA 6 19 H-G oltage H-G Current 8 Current [ka] - EF1 (Thy. Conv.) - EF1 (Ideal -source) Fwd. Conv. (EF1) Rev. Conv. (EF1) -6 -.1.1..3..5.6.7 H-G oltage [k] 7 18 6 5 17 -.1.1..3..5.6.7 H-G Current [ka] Fig. 1 Current waveforms of EF1 coil and thyristor converters. Fig. 1 Waveforms of AC voltage and current supplied by H-G. oltage [k] - - EF1 Fwd. Firing Angle EF1 Rev. Firing Angle EF1 oltage (Thy. Conv.) EF1 oltage (Ideal -source) 1 1 1 8 6 Firing Angle [deg] Active Power [W] Reactive Power [ar] Apparent Power [A] 3 1 Active Reactive Apparent..1 -.1 Power Factor -6-8 -.1.1..3..5.6.7 Fig. 11 Waveforms of EF1 coil voltage and firing angle for thyristor converters. This system is based on the circuit equations, and the control constants were also derived from the circuit parameters. The coil voltage is controlled via the converter output voltage during plasma breakdown. To provide the smooth coil current zero crossing, a circulating current between the forward and reverse converters is simultaneously controlled according to the coil current as shown in Fig. 7. Here, both the reference of the circulating current and the positive/negative thresholds of the coil current are fixed at half of the rating of the forward converters because of the asymmetric current rating between the forward and reverse converters. In this model, the periodic control interval is set to 1 ms equal to that in JT-6.. Results and Discussion Using the developed model, a PSI simulation was performed for the duration of t= 6 ms corresponding to plasma breakdown phase. The preliminary results are described below..1. Control Response of Thyristor Converter Figures 8 and 9 show the simulation result of current Fig. 13 Power Factor -1 -. -.1.1..3..5.6.7 Waveforms of AC power supplied by H-G and power factor. and voltage waveforms of EF6 coil. In those figures, the result in the case of the ideal voltage sources instead of the thyristor converters are also indicated for comparison. In addition, the current waveforms of the forward and reverse converters of Booster PS for EF6, and the firing angle for the forward converters are also shown for reference. The current waveform in the case of the thyristor converters gives close agreement with that in the case of the ideal voltage source. This agreement is contributed by the fast response of the feedforward control. However, it is found that the converter voltage control is delayed for approximate ms in compared with the ideal voltage source, and this delay leads to the discrepancy between the current waveforms of the thyristor converters and the ideal voltage source. At the initial coil current of EF6 (1.99 ka), Booster PS is operated in Forward ode with no circulating current. In this situation, since only the forward converters are working, the control response to the step input from small firing angle to large one is slow due to the natural commutation. Such a control delay can be also observed in Fig. 11. In this case, Booster PS for EF1 is operated in Circulating Current ode. Therefore, the control response depends on both of the forward and reverse converters. Is this situation, the step response of the forward converters is

K. Yamauchi et al., Electric Circuit Analysis for Plasma Breakdown in JT-6SA slow as in the above-mentioned case, and that of the reverse ones is fast. In Fig. 1, it is found that an overshoot of the circulating current appears at t= ms. This overshoot also implies the unbalance response between the forward and reverse converters... AC oltage and Power Figure 1 shows the waveforms of the AC voltage and current supplied by H-G. Although the output voltage of H-G is controlled by PI feedback regulation at 18 k, it is found that the voltage fluctuations are caused by the rapid load change started at t= ms and the internal impedance. Figure 13 indicates the waveforms of the AC power supplied by H-G and the power factor. An apparent power of about A is observed and the reactive power is strongly dominant. This result is half the rated capacity of H-G, however, is based on the case of no Base PSs. Actually, a higher reactive power must be observed. Therefore, for evaluation of the reactive power and the voltage drop, a further circuit analysis including Base PSs has to be conducted. References [1]. atsukawa et al., Status of JT-6SA tokamak under the EU-JA Broader Approach Agreement, Fusion Eng. Des., 83, 795 83 (8). []. atsukawa et al., Optimization of plasma initiation scenarios in JT-6SA, APFA 9 (to be published in JPFR Series). 5. Conclusions Using the modeling method mentioned in this paper, a circuit analysis including not only complex interactions but also nonlinear phenomenon can be performed. As one of the applications of it, a circuit analysis of the tokamak system JT-6SA was demonstrated using the PSI code. The purpose of the circuit analysis is to obtain stable plasma breakdown and for designing the details of a power supply system in JT-6SA. Some simulation results of plasma breakdown at t= 6 ms were preliminarily shown using an ideal voltage source and a thyristor converter model for comparison. As a result, the delay effect of the converter voltage control was summarized as the first achievement. Furthermore, the voltage fluctuations of H-G at plasma initiation and their influence were also described. As future works, some modifications are required to complete the modeling such as Base PSs and SNUs. Specifically, for evaluation of the reactive power and the voltage drop at H-G, a circuit analysis including Base PSs has to be performed. In addition, a realistic modeling of the DC current interrupter in SNU has to be conducted to investigate the influence of the delay and jitter. Ultimately, the plasma should be involved for analyzing and designing the details of a power supply system such as protection sequence in the case of a plasma disruption. Acknowledgements This work was supported within the framework of the Broader Approach Internationals Agreement. 5