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Time Evaluation of Diamagnetic Loop and Mirnov Oscillations in a Major Plasma Disruption and Comparison with a Normal Shot

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Time Evaluation of Diamagnetic Loop and Mirnov Oscillations in a Major Plasma Disruption and Comparison with a Normal Shot International Nano Letters https://doi.org/10.1007/s40089-018-0259-x ORIGINAL ARTICLE Time evaluation of diamagnetic loop and Mirnov oscillations in a major plasma disruption and comparison with a normal shot R. Sadeghi1 · Mahmood Ghoranneviss1 · M. K. Salem1 Received: 21 November 2018 / Accepted: 7 December 2018 © The Author(s) 2018 Abstract In this paper, plasma disruption was investigated in IR-T1 tokamak. Moreover, the time evaluation of plasma parameters such as plasma current, Ip; loop voltage, Vloop; power heating; and safety factor was illustrated. The results of diamagnetic loop and Mirnov oscillations in a major disruption were compared with their results in a normal shot. In addition, plasma disruption in diferent tokamaks was investigated and the results were compared with the IR-T1 tokamak. Keywords Disruption · Runaway electrons · Mirnov coils · Diamagnetic loop · Tokamak · MHD instability Introduction tokamak disruptions cause plasma confinement to be destroyed by restriction of current and density which ends Among various tools of magnetic confnement, tokamak to large mechanical stresses. Plasma disruption is caused containing hot plasma is one of the best and developed by strong stochastic magnetic feld formed due to nonlin- devices [1]. Tokamaks are divided into two groups: frst, the earity excited low-mode number magneto–hydro–dynamics large tokamaks for studying large plasmas such as DIII-D (MHD) modes. The safety factor (q) is very important in [2] and Tore–Supra [3] with high-cost testing conditions and determining stability and transport theory [9–13]. The paper second, small tokamaks such as STOR-M [4] and ISTTOK is organized as follows: in Sect. 2, time evaluation of plasma [5] which have close relationship with the frst group so that parameters and safety factor is summarized; Sect. 3 presents most of the experiments are initially carried out by them. time evaluation of diamagnetic loop and Mirnov oscillations One of the applications of tokamaks is in the feld of nano- in a major disruption. Moreover, the results are compared science. Neverov et al. [6] developed a theoretical model for with a normal shot; in Sect. 4, we investigate the plasma dis- neutron and X-ray difraction of carbon nanomaterials and ruption in the diferent tokamaks and fnally, Sect. 5 includes hydrocarbon flms deposited inside a vacuum vessel of the a summary and conclusions. tokamak T10. Nechaev and Alexeeva [7] answered to some problems about thermodynamic analysis of hydrogen storage in carbon-based nanomaterials with sp’ hybridization which The time evaluation of plasma parameters was used in atomic hydrogen adsorption in carbon nano- and safety factor structures. In addition, Kukushkin et al. [8] stimulated the fne structure of the deposited flms deposited in the vacuum The IR-T1 tokamak parameters in the disruptive discharges n̄ ∼ 1.5 × 1019m−3 vessel of high-temperature plasma such as stellarators and have the density limit e , the approxi- tokamaks. They also created the nanomaterials based on the mate plasma current ( 30 KA) is obtained for 5 ms approxi- carbon nanostructures. mately and the loop voltage is (2V) , major radius is 45 cm, IR-T1 tokamak is the small type of tokamak which is minor radius is 12/5 cm and toroidal feld is 1/0 T. used in this experiment. As an important phenomenon, Figure 1 shows the position of poloidal array of 12 Mirnov coils [14]. P * Mahmood Ghoranneviss ohmic is the rate of input heating power. The ohmic heat- [email protected] ing power is 1 1 Department of Physics, Faculty of Sciences, Science LI2 . Pohmic = VRIP − P and Research Branch, Islamic Azad University, Tehran, Iran 2 Vol.:(0123456789)1 3 International Nano Letters 30 20 (kA) Ip 10 0 0 5 10 15 20 25 30 35 Time (ms) (a) 20 10 olt) (V 0 Fig. 1 Vloop Position of poloidal array of 12 Mirnov coils -10 ̇ ̇ -20 If the plasma is in thermal equilibrium (L = 0, I = 0) , then 0 5 10 15 20 25 30 35 we have [15]: Time (ms) (b) Pohmic = VRIP. 400 Figures 2 and 3 show the experimental signals of a dis- charge (plasma current, loop voltage and heating power). 200 Figure 4 shows the time evaluation of safety factor. Major (kW) 0 disruption is observed in t = 20ms that annihilates plasma in wer Po t = 15ms.Pohmic is the rate of input heating power [15]. -200 In this section, we will compare experimental results in the -400 normal and disruption shots obtained in the IR-T1 tokamak. Heating -600 Plasma evaluations in a normal shot of IR-T1 tokamak, 0 5 10 15 20 25 30 35 Plasma evaluations during a disruption of IR-T1 tokamak. Time (ms) We conclude an increase in MHD oscillations and a loop (c) voltage peak in pre-disruption stage that generate high-energy runaway electrons. Fig. 2 a Plasma current, b loop voltage, c heating power in a normal With looking up to above plots in IR-T1 tokamak, we can shot say that regarding the short discharge duration, plasma disrup- tion will happen very soon and it produces runaway electrons. In this section, we have the time evaluation of safety evaluation of Mirnov oscillations. Figures 7 and 8 show the factor in IR-T1 tokamak. The safety factor, q, is so called time evaluation of diamagnetic loop. because of the role it plays it determining the stability. If We conclude that in pre-disruption stage, increase in q = m n , where m and n are integers, the feld line joins up MHD oscillations and loop voltage peak causes generation on itself after m toroidal and n poloidal rotations round the of high-energy runaway electrons. torus [1]. The safety factor (q) is very important in determining stability and transport theory. The plasma disruption in diferent tokamaks The time evaluation of diamagnetic loop In this section, we will investigate the plasma disruption and Mirnov oscillations in diferent tokamaks (JET, TEXTOR, TCV, COMPASS, ASDEX Upgrade, and MAST) and we will compare the In this section, we study time evaluation of Mirnov oscilla- results with the IR-T1 tokamak. tions and diamagnetic loop in IR-T1 tokamak in a normal In JET, a major disruption occurs in the time t = 14/5 (s), shot and a disruption shot. Figures 5 and 6 show the time and I = 1/2 MA and B = 1/2 T [16, 17]. 1 3 International Nano Letters 30 1 tion 0.5 20 cilla (kA) 0 Ip 10 ov Os -0.5 Mirn 0 0 5 10 15 20 25 30 35 -1 0 5 10 15 20 25 30 35 Time (ms) (a) Time (ms) 20 Fig. 5 Time evaluation of Mirnov oscillations in IR-T1 tokamak in a normal shot 10 olt) 1 (V 0 Vloop 0.5 -10 cillation-30 0 -20 0 5 10 15 20 25 30 35 Time (ms) ov Os -0.5 (b) Mirn -1 0 5 10 15 20 25 30 35 Time (ms) Fig. 6 Time evaluation of Mirnov oscillations in IR-T1 tokamak in a disruption shot 1 D2 0.5 0 D1, D2 -0.5 D1 -1 (c) 0 5 10 15 20 25 30 35 Time (ms) Fig. 3 a Plasma current, b loop voltage, c heating power in a disrup- tion shot Fig. 7 Time evaluation of diamagnetic loop in IR-T1 tokamak in a normal shot 3 In TEXTOR, disruption occurs in the time t = 2/01(s), and or 2 I = 350 KA and B = 2/4 T [18]. ct In TCV, disruption occurs in the time t = 1/5 (s), and ty Fa I = 200 KA and B = 1/43 T [19]. 1 Safe In COMPASS, disruption occurs in the time t = 1/12 (s), and I = 80 KA and B = 1/15 T [19]. 0 In ASDEX Upgrade, disruption occurs in the time t = 1 0 5 10 15 20 25 30 35 Time (ms) (s), and I = 0/8 MA and B = 2/5 T [19]. In MAST, disruption occurs in the time t = 0/5 (s) and I = 400 KA [20]. Fig. 4 Time evaluation of safety factor in IR-T1 tokamak In IR-T1, disruption occurs in the time t = 20 (ms) [15]. 1 3 International Nano Letters 1 mmons.org/licen ses/by/4.0/ ), which permits unrestricted use, distribu- tion, and reproduction in any medium, provided you give appropriate 0.5 D2 credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. 0 D1 , D2 -0.5 References D1 -1 1. Wesson, J.A.: Disruptions in JET. Nucl. Fusion 29, 641 (1989) 0 5 10 15 20 25 30 35 2. Burrell, K.H., Gohil, P., Groebner, R.J., Kaplan, D.H., Robinson, Time (ms) J.I., Solomon, W.M.: Improved charge-coupled device detectors for high-speed, charge exchange spectroscopy studies on the DIII- D tokamak. Rev. Sci. Instrum. 75, 3455 (2004) Fig. 8 Time evaluation of diamagnetic loop in IR-T1 tokamak in a 3. Hennequin, P., Honoré, C., Truc, A., Quéméneur, A., Fenzi- disruption shot Bonizec, C., Bourdelle, C., Garbet, X., Hoang, G.T.: Fluctuation spectra and velocity profle from Doppler backscattering on Tore Supra. Nucl. Fusion 46, S771 (2006) We conclude that plasma disruption occurs late in large 4. Onchi, T., Liu, Y., Dreval, M., McColl, D., Elgriw, S., Liu, D., tokamaks, but early in small tokamaks. Asai, T., Xiao, C., Hirose, A.: Efects of compact torus injection By the way, with looking up to the above plots in IR-T1 on toroidal fow in the STOR-M tokamak.
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