共查询到18条相似文献,搜索用时 343 毫秒
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在HT-7超导托卡马克装置上利用低杂波电流驱动有效地控制了等离子体电流分布,并使等离子体约束性能改善。数值模拟与硬X射线测量结果均表明,低杂波的发射功率谱、纵场和等离子体密度对改变等离子体电流分布有明显的影响。在优化低杂波电流驱动实验参数的条件下,等离子体密度、温度分布发生了理想的变化。在电子和离子温度分布上出现了内部输运垒,同时等离子体的能量约束时间和粒子约束时间均有提高。 相似文献
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在HL-1托卡马克上进行了辅助加热、加料、电流驱动的物理实验研究。在改善等离子体约束方面,某些实验取得了较好的结果。在适当的稳定放电条件下,低杂波电流驱动和弹丸注入辅助加料,均能使等离子体能量约束得到一定程度的改善,与相同密度条件下的欧姆加热放电相比,能量约束时间提高了约30%。在电子回旋共振加热等离子体实验中,等离子体总能量明显增加,但与相同密度条件下的欧姆加热放电相比,能量约束时间减少了约20%。 相似文献
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HL—1装置辅助加热等对能量约束的影响 总被引:1,自引:1,他引:0
在HL-1托卡马克上进行了辅助加热,加料,电流驱动的物理实验研究。在改善等离子约束方面,某些实验取得了较好的结果。在适当的稳定放电条件下,低杂波电流驱动和弹丸注入辅助加料,均能使等离子体能量约束得到一定程度的改善,与相同密度条件下的欧姆加热放电相比,能量约束时间提高了约30%。在电子回旋共振加热等离子体实验中,等离子体总能量明显增加,但与相同密度条件下的欧姆加热放电相比,能量约束时间减少了约20% 相似文献
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描述HL-1M装置上几种典型放电中的边缘等离子体物理实验结果.利用马赫/朗缪尔6探针组、静电4探针组、20组三探针阵列研究了低杂波电流驱动、超声分子束注入、多发弹丸注入和中性束注入放电中的粒子约束性能、等离子体旋转和边缘静电雷诺胁强的变化对改善约束的影响.给出了雷诺胁强和极向相速度的关系.结果表明,雷诺胁强的径向变化可以自发产生托卡马克等离子体的剪切极向流.LHCD能使低密度放电的粒子约束增加1至2倍.弹丸注入后,粒子约束时间和极向旋转至少可增加1倍,而SMBI可使粒子约束时间增加约一个数量级并取得高性能等离子体.
关键词:
粒子约束
雷诺胁强
极向流剪切
马赫/朗缪尔6探针组 相似文献
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用NaI闪烁体探测器组成的逃逸电子诊断系统和CdTe半导体探测阵列组成的快电子轫致辐射诊断系统,研究了一定等离子体密度条件下低杂波功率和等离子体电流对逃逸产生的影响以及一定低杂波功率下等离子体密度对逃逸电子产生的不同作用效果。根据实验数据计算了HT-7装置等离子体中电子逃逸的阈值电场和一定放电条件下电子逃逸的阈值能量。 相似文献
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《物理学报》2021,(18)
具备弱剪切或负磁剪切和内部输运势垒的托卡马克运行方式被认为是提高聚变性能的最有前途的方法.中空电流密度剖面与反磁剪切位形是改进堆芯约束和形成内部输运垒的关键条件之一.在中国环流器2号A(HL-2A)弹丸注入实验中,成功地实现了维持时间约为100 ms的中空电流放电.伴随着中空电流剖面的形成,同时形成了反磁剪切位形.由于欧姆加热功率不太高,且没有外部辅助加热,只能在稳定的中空电流放电阶段看到内部输运垒形成的趋势.在弹丸注入后,电子热扩散系数显著降低,说明弹丸深度注入改善了能量约束.等离子体性能的增强:一方面是由于弹丸注入造成中心高度峰化的电子密度剖面;另一方面是由于等离子体中心存在负磁剪切.同时,中空电流位形有利于改善高密度等离子体的稳定性.结果还表明,在中空电流放电中,等离子体比压值是低的.为了提高βN极限,可在等离子体边界附近放置导电壁.HL-2A弹丸注入实验的结果,为在限制器托卡马克上获得高参数放电提供了一种可能. 相似文献
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EAST等离子体高约束模运行条件下,在等离子体边缘区域观测到明显的等离子体电流带.在EAST托卡马克装置非圆截面平衡位形下,使用射线追踪方法研究低混杂波高平行折射率N‖分量对电流驱动的影响.结果表明:当-8≤N‖≤-6时,平行折射率分量能够在小半径(0.7 < r/a < 1)区域驱动kA量级的等离子体电流.对于具有台基区、等离子体边缘温度更高的电子温度剖面,驱动电流的位置r/a>0.9.低混杂波朗道阻尼的理论分析与数值模拟结果一致.另外,高N‖低混杂波在等离子体边缘的功率沉积和电流驱动与电子温度分布和发射谱分布相关. 相似文献
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HT-6M托卡马克通过边界欧姆加热实现了改善约束的H模,利用中性粒子测量方法成功地研究了等离子体H模放电的中性粒子变化.观察到边界欧姆加热H模放电期间从等离子体逃逸的中性粒子比纯欧姆加热明显减少;约束改善后等离子体中心热区的中性原子密度下降,得到了反映等离子体约束改善的中性粒子特征.实验结果与其他诊断进行了比较和讨论
关键词: 相似文献
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A new method using special shape parameters has been introduced to study density behavior with synergy of lower hybrid current drive (LHCD) and ion Bernstein wave (IBW) heating in the HT-7 superconducting tokamak. During the synergy of the LHCD and IBW heating an improved confinement plasma was achieved, and the electron density was increased and peaked. 相似文献
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Shvyd'ko YV Lerche M Jäschke J Lucht M Gerdau E Gerken M Rüter HD Wille HC Becker P Alp EE Sturhahn W Sutter J Toellner TS 《Physical review letters》2000,85(3):495-498
H-mode operation has been achieved in high current (I(p)>200 kA) plasmas in the START spherical tokamak for both neutral-beam-injection-heated and Ohmic discharges. The transition to H mode features the development of well-defined edge pedestals in density and temperature, which signifies the formation of an edge-transport barrier, and associated edge-localized modes. Recent operation at plasma currents exceeding 250 kA shows that these features are accompanied by increases in energy confinement time. This is the first clear demonstration of the H-mode regime in a spherical tokamak. 相似文献
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H-mode discharges with lower hybrid current drive (LHCD) alone are achieved in EAST divertor plasma over a wide parameter range. These H-mode discharges are characterized by a sudden drop in Dα emission and a spontaneous rise in main plasma density. Good lower hybrid (LH) coupling during H-mode is obtained by putting the plasma close to the antenna and by injecting D2 gas from a pipe near the grill mouse. The analysis of lower hybrid current drive properties shows that the LH deposition profile shifts off axis during H-mode, and current drive (CD) efficiency decreases due to the increase in density. Modeling results of H-mode discharges with a general ray tracing code GENRAY are reported. 相似文献
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In this paper the density profile behaviour and the particle confinement operation regime on HL-1M have been studied under the pellet injection (PI), supersonic molecular beam injection (SMBI), gas puffing (GP) and lower hybrid current drive experimental situations. The relationships between density profile, particle confinement time and edge safe factor have been explored. The density profile, which is measured by six-channel far-infrared ray laser interferometer has been analysed by using the peaking coefficient calculation code. Changes of the outward and inward diffusion velocities before and after the peaking of the central density profile have been calculated using the global particle balance equations. The particle confinement operation regimes have been discussed. The peaking density profile can be easily obtained under the condition of efficient fuelling. In ohmic discharges, confinement time increases as the peaking density profile factor rises, and is saturated at a critical value related to the fuelling efficiency. The particle confinement time of SMBI lies between the values of GP and PI, and its value is about 3-5 times of the energy confinement time. 相似文献
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Fujita T Ide S Kamada Y Suzuki T Oikawa T Takeji S Sakamoto Y Koide Y Isayama A Hatae T Kubo H Higashijima S Naito O Shirai H Fukuda T 《Physical review letters》2001,87(8):085001
A quasisteady reversed shear plasma with a large bootstrap current fraction ( approximately 80%) has been obtained for the first time in the JT-60U tokamak. The shrinkage of reversed shear region was suppressed by the bootstrap current peaked at the internal transport barrier (ITB) layer and the ITBs at a large radius were sustained, which, by combination with an H-mode edge pedestal, resulted in a high confinement or 2.2 times the H-mode scaling for 6 times energy confinement time or 2.7 s. Furthermore, a full noninductive current drive was obtained by the bootstrap current and the beam driven current. 相似文献