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Physics of high performance JET plasmas in DT

机译:DT中高性能JET等离子体的物理

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Abstract. The Joint European Torus (JET) has recently operated with deuterium-tritium (DT) mixtures, carried out an International Thermonuclear Experimental Reactor (ITER) physics campaign in hydrogen, deuterium, DT and tritium, installed the Mark IIGB ‘Gas Box' divertor fully by remote handling and started physics experiments with this more closed divertor. The DT experiments set records for fusion power (16.1 MW) f ratio of fusion power to plasma input power (0.62, and 0.95 ± 0.17 if a similar plasma could be obtained in steady state) and fusion duration (4 MW for 4 s). A large scale tritium supply and processing plant, the first of its kind, allowed the repeated use of the 20 g of tritium on-site to supply 99.3 g of tritium to the machine. The H mode threshold power is significantly lower in DT, but the global energy confinement time is practically unchanged (no isotope effect). Dimensionless scaling‘wind tunnel' experiments in DT extrapolate to ignition with ITER parameters. The scaling is close to gyro-Bohm, but the mass dependence is not correct. Separating the thermal plasma energy into core and pedestal contributions could resolve this discrepancy (leading to proper gyro-Bohm scaling for the core) and also account for confinement degradation at high density and at high radiated power. Several radiofrequency heating schemes have been tested successfully in DT, showing good agreement with calculations. Alpha particle heating has been clearly observed and is consistent with classical expectations. Internal transport barriers have been established in optimized magnetic shear discharges in DT and steady state conditions have been approached with simultaneous internal and edge transport barriers. First results with the newly installed Mark IIGB divertor show that the in- out symmetry of the divertor plasma can be modified using differential gas fuelling, that optimized shear discharges can be produced and that krypton gas puffing is effective in restoring L mode edge conditions and establishing an internal transport barrier in such discharges.
机译:抽象。欧洲联合圆环(JET)最近使用氘-((DT)混合物运行,在氢气,氘,DT和ium中进行了国际热核实验堆(ITER)物理活动,并完全安装了Mark IIGB的“气体箱”分流器通过远程操作并使用该更封闭的偏滤器开始物理实验。 DT实验创下了聚变功率(16.1 MW)f聚变功率与等离子体输入功率之比(0.62,如果在稳态下可获得相似的等离子体,则为0.95±0.17)和聚变持续时间(4 MW,持续4 s)的记录。大型tri供应和加工厂,这是同类产品中的第一个,它允许现场重复使用20克to,以向机器提供99.3克of。在DT中,H模式的阈值功率明显较低,但是总体能量约束时间实际上没有变化(没有同位素效应)。 DT中的无量纲缩放“风洞”实验可通过ITER参数外推到点火。缩放比例接近陀螺-波姆,但是质量相关性不正确。将热等离子体能量分为核心和基座贡献可以解决此差异(导致核心有适当的陀螺-博姆缩放比例),并且还可以解决高密度和高辐射功率下的约束退化。 DT中已成功测试了几种射频加热方案,与计算结果显示出良好的一致性。已经清楚地观察到Alpha颗粒加热,并且与经典预期一致。已经在DT中优化了磁剪切放电的过程中建立了内部运输壁垒,并且同时使用内部和边缘运输壁垒达到了稳态条件。新安装的Mark IIGB偏滤器的初步结果表明,可以使用差分气体燃料来改变偏滤器等离子体的进-出对称性,可以产生最佳的剪切放电,gas气的吹气对恢复L型边缘条件和建立有效这种排放中的内部运输障碍。

著录项

  • 来源
    《Nuclear fusion》 |1999年第9期|p.1227-1243|共17页
  • 作者

    JET Team;

  • 作者单位
  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子核物理学、高能物理学;
  • 关键词

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