Study of confinement improvement in presence of a MARFE in the HT-7 superconducting tokamak

Abstract

A new set of actively cooled toroidal double-ring graphite limiters have been developed on the HT-7 tokamk for long pulse operation. In this paper, a Multifaceted asymmetric radiation from the edge (MARFE) phenomena and improved particle confinement induced by a MARFE, characterized by Halpha line emissions drops and the line-averaged density increase have been studied in the HT-7 ohmic discharges (where the plasma current Ip=145 kA, loop voltage Vloop =2-3 V, toroidal field B T =1.7 T, and Zeff =2-8). It is found that the improved particle confinement phase exists for about 90 ms and the particle confinement time tP increased about 1.6 times.

Confinement Improvement; Graphite limiters; MARFE

REGULAR ARTICLES

Study of confinement improvement in presence of a MARFE in the HT-7 superconducting tokamak

M. Asif^I,II; HT-7 Team

^IInstitute of Plasma Physics, Chinese Academy of Sciences, P.O. Box 1126, Hefei, Anhui 230031, P. R. China

^IIApplied Physics Division, PINSTECH, Islamabad 04770, Pakistan

ABSTRACT

A new set of actively cooled toroidal double-ring graphite limiters have been developed on the HT-7 tokamk for long pulse operation. In this paper, a Multifaceted asymmetric radiation from the edge (MARFE) phenomena and improved particle confinement induced by a MARFE, characterized by H_a line emissions drops and the line-averaged density increase have been studied in the HT-7 ohmic discharges (where the plasma current I_p=145 kA, loop voltage V_loop =2-3 V, toroidal field B_T =1.7 T, and Z_eff =2-8). It is found that the improved particle confinement phase exists for about 90 ms and the particle confinement time t_P increased about 1.6 times.

Keywords: Confinement Improvement; Graphite limiters; MARFE

I. INTRODUCTION

Operating at high density, the MARFE phenomenon usually develops before reaching the density limit. The term 'MARFE' [1, 2] is an acronym for 'multifaceted asymmetric radiation from the edge' and defines a toroidally symmetric and poloidally asymmetric belt of high density, strongly radiating, cold plasma localized at the high field side of a limiter tokamak. In some cases, the MARFE can extend all around the poloidal cross-section, thus detaching the main hot plasma from the first wall. The phenomenon is of interest both as a precursor of the density limit and, because of its capability of radiating power, as a means of reducing localized thermal loads on the wall of a fusion reactor. MARFE phenomena has been observed on many tokamaks [1,3].

In the TEXTOR-94 limiter tokamak, the highest critical density can be obtained up to 130-200% of the Greenwald density limit n_GW [4], (for circular plasmas: n_GW=I_P/pa², where n_GW is the line-averaged density in units of 10²⁰ m ^{- 3}), by the controlled localized recycling [5]. In the Tore Supra superconducting tokamak [6], the critical density is only 12-22% of the Greenwald limit. In the HT-7 superconducting tokamak, the averaged density of MARFE onset (Z_eff = 3-8 and 15-30% of the Greenwald limit [7-8]) is also observed to be very low in the discharges of each campaign before the wall conditioning [9-10]. However, after rf- boronization in the HT-7 [10], the MARFE onset density is more than 120% of n_GW[7-8]. With good wall conditioning (e.g., fresh siliconization and fresh boronization) in the TEXTOR-94 [11], the appearance of MARFE's has been postponed up to 170% of the Greenwald limit. The critical conditions for the occurrence of a MARFE may be correlated to the edge plasma parameters, because it is a localized instability within the edge region. It was evidence that the critical value of n_e(0.7a)Z_eff in the MARFE onset always correlated with the total input power which has been observed in the FTU [12] and the HT-7 limiter tokamak [7-8], here n_e(0.7a) is the line average density, measured at the outermost interferometer channel at r =20 cm (r =0.7a, the minor radius a = 27 ~ 28 cm). In the TEXTOR-94, dependence of the edge electron density (r = a+1 cm) on the heating power was also observed [13]. Therefore, it suggests experimentally the importance of impurity radiation and localized power balance in the MARFE formation.

Experiments in the TFTR tokamak [14-16] illustrate the sequence of MARFE formation and evolution to a detached H-mode-like plasma: a MARFE triggered at some position on the inner periphery of the minor cross section of the plasma cools the plasma edge further causing the minor radius to shrink and the plasma to thus pull away from the walls and limiters. In the detached state the electron temperature and density profiles are narrower and ~ 100% of the input power is radiated away by impurities in the edge layer. In the TEXTOR tokamak the MARFE generally leads to a disruption. In the FTU tokamak the onset of a MARFE always occurs before achieving the density limit [12]. The critical density for its onset is not a constant for the same magnetic field and plasma current, but depends on the vacuum vessel conditioning procedure and on the material used for the limiter surface [17].

Many machines were operated for the mixed carbon material used for long pulse operation, ultimately steady state. The graphite based first wall components have been designed and tested to sustain particle and heat exhausts under steady state conditions in Tore Supra [18]. A major part of DIII-D [19] program is focused upon high performance experiments. HT-7 is a superconducting tokamak [20] with the limiter configuration designed to operate with high power and long duration discharge. The last closed flux surface was defined by the main poloidal limiter in 1999, which receives the highest heat loads and largest flux of energetic particles bombardment from the plasma. In past operations with Mo limiter, due to energetic particles bombardment and overheating problem, the plasma discharge was usually terminated by the very strong hard X-ray radiation, hot spot and high-Z impurities. In order to alleviate above problems, a new set of actively cooled toroidal double-ring graphite limiters [21], has been developed in the Hefei Tokamak-7 (HT-7) superconducting tokamak in 2004. The doped graphite GBST1308 with the dopant concentration of 1%B, 2.5%Si , 7.5%Ti, (about 20 % of first wall) was used as limiter material [21]. Very stable and reproducible discharges were obtained with significantly increased density and a large increase in the available pulse length, as compared to Mo limiters. Up to 240 s of long pulse discharge has been achieved by lower hybrid current drive (LHCD) with new graphite limiters [22] in the HT-7 in 2004.

In this paper, a Multifaceted asymmetric radiation from the edge (MARFE) phenomena and improved particle confinement induced by a MARFE, characterized by H_a line emissions drops and the line-averaged density increase have been studied in the HT-7 ohmic discharges (where the plasma current I_p=145 kA, loop voltage V_loop =2-3 V, toroidal field B_T =1.7 T, and Z_eff =2-8). It is found that the improved particle confinement phase exists for about 90 ms and the particle confinement time t_P increased about 1.6 times.

II. EXPERIMENTAL SETUP

The Hefei Tokamak-7 (HT-7) is a superconducting tokamak [7-8, 21-26], and it was reconstructed from the original Russian T-7 tokamak in 1994. It has a major radius of R = 1.22 m, minor radius of a = 0.27 m in the circular cross section. There are two layers of thick copper shells, and between them are located 24 superconducting coils which can create and maintain a toroidal magnetic field (B_T) of up to 2.5 T. Based on the understanding of plasma surface interactions, several technical improvements have been made recently. The new GBST1308 doped graphite was used as limiter material. All carbon titles were coated with 100 µm Silicon Carbide (SiC) functional gradient coating [21]. The two poloidal water-cooling limiters and one toroidal water-cooling belt limiter at high field side were developed in 2002 [21]. A new set of actively cooled toroidal double-ring graphite limiters [22], at bottom and top of the vacuum vessel was developed for long pulse operation, and up to 240 s of long pulse plasma has been achieved in the HT-7 in 2004 as shown in Fig. 1.

The major research fields on the HT-7 are steady-state operation, high-performance such as advanced tokamak operation modes, the fuelling study [27] and MARFE phenomena [28], lower hybrid wave (LHW) current drive [29] and ICRF heating [30]. For recent experiments on the HT-7, the following main diagnostics signals are effectively used in this paper as shown in Fig. 2: a 16-channel XUV bolometer array to measure plasma radiation losses, a 7-channel bremsstrahlung emission (Z1 ~ 7) to measure Z_eff , a multichannel H_a (D_a) radiation array for t_P, 10-channels CIII line emission, an impurity optical spectrum measurement system and the electron density profile measured by a vertical 5-channel far-infrared (FIR) hydrogen cyanide (HCN) laser interferometer [31-32]. The laser source used in the interferometer was a continuous-wave (CW) DC glow discharge HCN laser with 3.4 m cavity length and 100 mW power output at 337 mm wavelength. The system has a temporal resolution of 0.1 ms with a 10 kHz rotating grating [32].

III. MARFE PHENOMENA AND IMPROVED PARTICLE CONFINEMENT

The MARFE may lead to improved confinement by cooling the edge at some times. The observed sequence of events for the formation of the MARFE and subsequent evolution into a detached plasma is as follows [33]. As radiating impurities accumulate in the plasma edge, a poloidally uniform band of radiating impurities is formed; then, as the plasma density or impurity density is increased, the poloidally uniform band goes through a transition into a stable, poloidally asymmetric distribution of radiating impurities-the MARFE, still located in the plasma edge, which ultimately becomes highly localized in tokamaks. Then, as the plasma or impurity density is further increased, the impurities undergo a further transition back into a poloidally uniform band. Since the radiative cooling of the edge has been increasing with increasing density, in this final state the plasma is detached or nearly detached.

Figure 3 shows the typical shot of experimental campaign 2004 (shot No.66362) on HT-7 with graphite limiters, the plasma current about 145 kA, the loop voltage V_loop < 2-3 V, the toroidal field B_T =1.7 T, Z_eff =2.5, R=1.22 m,a=0.27 m, the electron temperature T_e=600 eV and the line-averaged density about 5.4x10¹⁹ m ^{- 3}. A typical position of the MARFE on the HT-7 (shot No.66362) is identified by visible CIII (Channels 4 and 10) line emission as shown in Fig. 3. The MARFE occurs in the plasma column on the inner high field side. The MARFE onset is characterized by a sudden modification of visible CIII (Channels 4 and 10) line emission signal. It is clear that MARFE event occurs from t =215 ms suddenly as shown in Fig. 3.

It must be mentioned that a radiatively improved confinement mode, on the HT-7 with molybdenum limiter has been observed [34-35], and the improved confinement mode phase is maintained for about 40 ms. Fig. 4 shows the plasma current I_p, multichannel H_a emission (Pd7, Pd8, Pd10, Pd12), CIII emission from channels 4 and 10, in current experiments with graphite limiters on HT-7. It is found that the improved particle confinement phase, which is characterized by multichannel H_a emission (Pd7, Pd8, Pd10, Pd12) drop and the line-averaged density increase, is observed clearly from t=225 ms in Fig. 4, exists for about 90 ms and the particle confinement time t_P increased about 1.6 times.

Figure 3 (c) shows the core plasma central electron density increases during onset of improved particle confinement phase, and that if the neutral concentration increases, the MARFE density limit decreases, which were expected from the theory [36] has not measured by direct diagnostics on the HT-7 limiter tokamak.

The density profile is studied and shows that the profile become narrow and more peaked. Fig. 5 shows the electron density profiles at t=210 ms (before the event trigger) and t=306 ms (before the end of improved particle confinement phase). The particle confinement is improved and the density profile is clearly changed from t=210 ms to the improved particle confinement phase, t=306 ms.

In the HT-7 superconducting tokamak with molybdenum limiter [8], the onset of a MARFE usually occurs in the early ohmic discharges (Z_eff = 3 ~ 8 and 15% ~ 25% of the n_GW) of each experimental campaign before wall conditioning. In HT-7 with graphite limiters [22], the critical density of MARFE onset is observed in the ohmic discharges (Z_eff = 2 ~ 8 and 80% ~ 100% of the n_GW). The best correlation has been found between the total input ohmic power and the product of the line average density, measured at the outermost interferometer channel at r = 20 cm (r/a @ 0.7, the minor radius a = 27 ~ 28 cm), and Z_eff. Under same injected power, the critical density with graphite (C) limiters is much higher than Mo limiter [see Fig. 6].

In the HT-7 tokamak high-Z_eff discharges, it is found that the MARFE occurs at values of = 0.5 ~ 0.7, where f_GW = , (Here _e is the maximum line average electron density and n_GW is the Greenwald density), with molybdenum limiter [8]. The critical factor of MARFE onset is 0.9 ~ 1.2 with graphite limiters (see Fig. 7).

However in the HT-7 tokamak the occurrence of a MARFE is not only correlated with the density but also with Z_eff. A quantitative comparison of impurity reduction via density is shown in Fig. 8 for Mo and C limiter materials. The main impurities were reduced in case of graphite limiter. The density limit appeared to be connected with the impurity content [see Fig. 8] and the edge parameters, and the best results, significantly increased density and a large increase in the available pulse length (see Fig.1) were obtained. Moreover, Improved particle confinement phase induced by a MARFE were observed for about 90 ms [see Fig.4], and the particle confinement time t_P increased about 1.6 times.

IV. CONCLUSIONS

A new set of actively cooled toroidal double-ring graphite limiter has been developed in the HT-7 superconducting tokamak for long pulse operation. A Multifaceted asymmetric radiation from the edge (MARFE) phenomena and improved particle confinement induced by a MARFE, characterized by H_a line emissions drops and the line-averaged density increase have been studied in the HT-7 ohmic discharges (where the plasma current I_p=145 kA, loop voltage V_loop =2-3 V, toroidal field B_T =1.7 T, and Z_eff =2-8). It is found that the improved particle confinement phase exists for about 90 ms and the particle confinement time t_P increased about 1.6 times. The results are similar to the experiments in TFTR [13], and are consistent with the theoretical explanation [33] given for the TFTR results. The MARFE cools the plasma edge, and the electron density profile is observed to become more narrow and peaked. In the HT-7, the occurrence of a MARFE is strongly correlated with the Z_eff and the wall condition but not with electron density.

Acknowledgements

The authors wish to thank the HT-7 team for cooperation during these experiments.

Received on 24 May, 2006

• [1] B. J. Lipschultz, J. Nucl. Mater. 145-147, 15 (1987).
• [2] N. Hosogane, N. Asakura, H. Kubo, K. Itami, A. Sakasai, J. Nucl. Mater. 196-198, 750 (1992).
• [3] D. R. Baker, R. T. Snider, and M. Nagami, Nucl. Fusion 22, 807 (1982).
• [4] M. Greenwald, J. L. Terry, S. M. Wolfe, S. Ejima, M. G. Bell, S. M. Kaye, and G. H. Neilson, Nucl. Fusion 28, 2199 (1988).
• [5] P. C. De Vries, J. Rapp, F. C. Schuller, and M. Z. Tokar, Phys. Rev. Lett. 80, 3519 (1998).
• [6] T. E. Evans, M.Goniche, A.Grosman, D.Guilhem, W. Hess, and J. C. Vallet, J. Nucl. Mater. 196-198, 421 (1992).
• [7] X. Gao, Y. Jie, C. Xia, M. Wei, Y. Yang, S. Zhang, J. Zhao, L. Hu, Y. Zhu, J. Luo, Y. Zhao, N. Qiu, J. Li, B. Wan, G. Kuang, X. Zhang, X. Liu, X. Gong, Y. Bao, B. Lin, Z. Wu, Y. Li, Y. Shi, M. Song, P. Fu, X. Zhang, M. Zeng, A. Xie, N. Cui, H. Ruan, L. Wang, B. Sheng, S. Liu, W. Ye, K. Yang, J. Liu, Y. Cheng, H. Fan, S. Liu, X. Tong, J. Mao, X. Gu, J. Xie, and Y. Wan, Nucl. Fusion 40,1875 (2000).
• [8] X. Gao, J. R. Luo, Y. P. Zhao, N. Qiu, Y. X. Jie, Y. Yang, C. Y. Xia, B. N. Wan, G. L. Kuang, X. D. Zhang, J. G. Li, F. X. Yin, X. N. Liu, X. Z. Gong, S. Y. Zhang, J. Y. Zhao, L. Q. Hu, Z. W. Wu, Y. D. Li, K. Yang, Y. Bao, W. W. Ye, L. Chen, H. Y. Fan, S. X. Liu, Y. F. Chen, B. L. Lin, Y. H. Xu, Y. J. Shi, M. Song, X. M. Zhang, M. S. Wei, M. Zeng, A. G. Xie, N. Z. Cui, H. L. Ruan, L. Wang, B. Sheng, S. Liu, X. D. Tong, X. M. Gu, J. S. Mao, J. K. Xie, and Y. X. Wan, J. Nucl. Mater. 279, 330 (2000).
• [9] J. K. Xie, Y. P. Zhao, J. Li, B. N. Wan, X. Z. Gong, J. S. Hu, X. Gao, X. M. Gu, S. D. Zhang, X. M. Wang, Y. Z. Mao, X. K. Yang, M. Zhen, S. Y. Zhang, and HT-7 team, J. Nucl. Mater. 290-293, 1155 (2001).
• [10] J. Li, Y. P. Zhao, X. M. Gu, C. F. Li, B. N. Wan, X. D. Zhang, J. R. Luo, X. Z. Gong, J. K. Xie, Y. X. Wan, P. J. Qin, X. M. Wang, Y. D. Meng, S. F. Li, X. Gao, Y. Yang, D. Y. Xue, Y. Z. Mao, X. Den, L. Chen, Y. C. Fang, F. X. Yin, S. X. Liu, X. K. Yang, D. Zhen Xu, J. Y. Ding, Y. X. Jie, Q. C. Zhao, J. S. Mao, S. Y. Zhang, J. Y. Zhao, J. S. Hu, H. Y. Fan, M. S. Wei, B. L. Lin, G. X. Wang, Y. D. Fang, and W. C. Shen, Nucl. Fusion 39, 973 (1999).
• [11] J. Rapp, W. Biel, H. Gerhauser, A. Huber, H. R. Koslowski, M. Lehnen, V. Philipps, A. Pospieszczyk, D. Reiser, U. Samm, G. Sergienko, M. Z. Tokar, and R. Zagórski, J. Nucl. Mater. 290-293, 1148 (2001).
• [12] D. Frigione, L. Pieroni, V. Zanza, G.M. Apruzzese, F. Alladio, M.L. Apicella, R. Bartiromo, M. Borra, G. Bracco, G. Buceti, P. Buratti, C. Centioli, M. Ciotti, V. Cocilovo, I. Condrea, F. Crisanti, R. de Angelis, B. Esposito, A. Frattolillo, G. Gatti, E. Giovannozzi, G. Granucci, M. Grolli, A. Imparato, H. Kroegler, M. Leigheb, L. Lovisetto, G. Maddaluno, G. Mazzitelli, P. Micozzi, S. Migliori, A. Moleti, F. Orsitto, D. Pacella, L. Panaccione, M. Panella, V. Pericoli-Ridolfini, S. Podda, G.B. Righetti, E. Sternini, A.A. Tuccillo, O. Tudisco, F. Valente, V. Vitale, and M. Zerbini, Nucl. Fusion 36, 1489 (1996).
• [13] J. Rapp, P.C. De Vries, F.C. Schüller, M.Z. Tokar, W. Biel, R. Jaspers, H.R. Koslowski, A. Krämer-Flecken, A. Kreter, M. Lehnen, A. Pospieszczyk, D. Reiser, U. Samm, and G. Sergienko, Nucl. Fusion 39, 765 (1999).
• [14] C. E. Bush, J. Schivell, J. D. Strachan, R. V. Budny, S. Cohen, B. Grek, A. Janos, D. W. Johnson, D. Manos, D. K. Mansfield, D. Mueller, H. H. Towner, R. M. Wieland and S. Yoshikawa, J. Nucl. Mater. 176-177, 792 (1990).
• [15] J. D. Strachan, F. P. Boody, C. E. Bush, S. A. Cohen, B. Grek, L. Grisham, F. C. Jobes, D. W. Johnson, D. K. Mansfield, S. S. Medley, W. Morris, H. K. Park, J. F. Schivell, G. Taylor, K. L. Wong, S. Yoshikawa, M. C. Zarnstorff, and S. J. Zweben, J. Nucl. Mater. 145-147, 186 (1987).
• [16] J. F. Schivell, C. E. Bush, D. K. Mansfield, S. S. Medley, H. K. Park, and F. J. Stauffer, Fusion Technol. 15, 1520 (1989).
• [17] F. Alladio, M. L. Apicella, G. Apruzzese, E. Bartiromo, O. Borra, G. Bracco, G. Buceti, P. Buratti, C. Centioli, M. Ciotti, V. Cocilovo, I. Condrea, F. Crisanti, R. DeAngelis, B. Esposito, C. Ferro, G. Franzoni, D. Frigione, L. Gabellieri, E. Giovannozzi, G. Granucci, M. Grolli, A. Imparato, H. Kroegler, M. Leigheb, L. Lovisetto, G. Maddaluno, G. Mazzitelli, P. Micozzi, A. Moleti, F. Orsitto, L. Panaccione, D. Pacella, M. Panella, V. Pericoli, L. Pieroni, S. Podda, G. B. Righetti, F. Romanelli, S. E. Segre, E. Sternini, A. A. Tuccillo, O. Tudisco, F. Valente, V. Vitale, R. Zagorski, V. Zanza, and M. Zerbini, Plasma Phys. Control. Fusion 36, B253 (1994).
• [18] M. Lipa, P. Chappuis, and P. Deschamps, Fusion Technol. 19, 2041 (1991).
• [19] G. L. Jackson, D. R. Baker, K. L. Holtrop, S. Konoshima, R. Maingi, G. M. Staebler, and W. P. West, J. Nucl. Mater. 220-222, 173 (1995).
• [20] X. Gao, Y. X. Jie, Y. Yang, C. Y. Xia, M. S. Wei, S. Y. Zhang, Y. F. Cheng, L. Q. Hu, J. S. Mao, X. D. Tong, B. N. Wan, G. L. Kuang, J. G. Li, Y. P. Zhao, J. R. Luo, N. Qiu, K. Yang, G. Li, J. K. Xie, and Y. X. Wan, Phys. Plasmas 7, 2933 (2000).
• [21] X. Gao, J. Li, Y. Yang, J. K. Xie, J. R. Luo, J. Y. Zhao, X. Z. Gong, L. Q. Hu, X. D. Zhang, Y. J. Shi, B. N. Wan, K. Tanaka, R. Sakamoto, Y. P. Zhao, G. L. Kuang , J. S. Hu, M. Asif, Y. X. Jie, H. Q. Liu, J. Liu, Q. Xu, L. Gao, and the HT-7 Team, J. Nucl. Mater. 337-339, 835 (2005).
• [22] M. Asif, X. Gao, J. Li, G. L. Kuang, B. N. Wan, Y. X. Jie, J. Y. Zhao, X. D. Zhang, H. Q. Liu, X. D. Tong, J. Liu, Q. Xu, J. S. Hu, Y. Yang, B. Shen, J. S. Mao, L. Q. Hu, Z. W. Wu, B. L. Ling and HT-7 Team, Phys. Plasmas 12, 082502 (2005).
• [23] M. Asif, X. Gao, J.G. Li, B.N. Wan and HT-7 Team, Phys. Lett. A. 336, 61 (2005).
• [24] M. Asif, X. Gao, J.G. Li, B.N. Wan and HT-7 Team, Phys. Lett. A. 342, 175 (2005).
• [25] M. Asif, X. Gao and HT-7 Team, Phys. Lett. A. 346, 305 (2005).
• [26] M. Asif, X. Gao and HT-7 Team, Phys. Lett. A. 349, 250 (2006).
• [27] Y. Yang, Y. Bao, J. Li, X. Gu and Y. He, Nucl. Fusion 39, 1871 (1999).
• [28] X. Gao and HT-7 Team, Plasma Sci. Technol. 1, 25 (1999).
• [29] G. Kuang, Y. Liu, J. Shan, W. Xu, X. Zhang, D. Liu, F. Liu, Y. Zhu, C. Zhang, G. Zheng, J. Wu, J. Lin, B. Ding, H. Xu, Y. Fang, J. Li, J. Luo, X. Zhang, B. Wan, Q. Zhao, J. Mao, X. Gao, S. Zhang, C. Li, X. Gu, P. Qing, H. Fan, S. Liu, B. Ling, B. Ding, Y. Li, Z. Wu, Y. Jie, S. Liu, J. Xie, and Y. Wan, Nucl. Fusion 39, 1769 (1999).
• [30] Y. P. Zhao J. Li, J. K. Xie, Y. D. Meng, X. C. Wu, Y. X. He, D. Y. Xue, X. Deng, and Y. G. Shao, Chin. Phys. Lett. 14, 916 (1997).
• [31] X. Gao, H. J. Lu, Q. L. Guo, Y. X. Wan, and X. D. Tong, Rev. Sci. Instrum. 66, 139 (1995).
• [32] Y. X. Jie, X. Gao, Y. F. Cheng, K. Yang, and X. D. Tong, Int. J. Infrared Millimeter Waves 21, 1375 (2000).
• [33] W. M. Stacey, Phys. Plasmas 3, 2673 (1996).
• [34] X. Gao, Y. P. Zhao, J. R. Luo, Y. X. Jie, X. Z. Gong, B. N. Wan, J. G. Li, F. X. Yin, G. L. Kuang, X. D. Zhang, S. Y. Zhang, N. Qiu, X. N. Liu, J. Y. Zhao, Y. Yang, Y. Bao, B. L. Lin, Z. W. Wu, Y. D. Li, Y. H. Xu, K. Yang, G. X. Wang, W. W. Ye, L. Chen, Y. J. Shi, M. Song, X. M. Zhang, P. J. Qin, X. M. Gu, N. Z. Cui, H. Y. Fan, S. X. Liu, Y. F. Chen, L. Q. Hu, J. S. Hu, C. Y. Xia, H. L. Ruan, X. D. Tong, J. S. Mao, J. K. Xie, and Y. X. Wan, Plasma Phys. Control. Fusion 41, 1349 (1999).
• [35] X. Gao, J. K. Xie, Y. X. Wan, K. Ushigusa, B. N. Wan, S. Y. Zhang, J. Li, and G. L. Kuang, Phys. Rev. E 65, 017401 (2001).
• [36] W. M. Stacey, Plasma Phys. Control. Fusion 39, 1245 (1997).

Publication Dates

• Publication in this collection
  16 Oct 2006
• Date of issue
  Sept 2006

History

• Received
  24 May 2006