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ICRF HEATING OF DEUTERIUM-TRITIUM PLASMAS IN TFTR

机译:TFTR中氘-等离子体的ICRF加热

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The first experiments to heat D-T plasmas in the ion cyclotron range of frequencies (ICRF) have been performed on the Tokamak Fusion Test Reactor (TFTR). These experiments have two major objectives: to study the RF physics of ICRF-heated D-T plasmas and to enhance the performance of D-T discharges. Experiments have been conducted at 43 MHz with out-of-phase current strap excitation to explore n_T_e concentrations up to approximately 40%. In these experiments n_T_e was limited by D recycling from the carbon walls. The location of the T resonance was varied by changing the toroidal magnetic field, and the RF power was modulated (f_(mod) = 5-10 Hz) to elucidate competing heating mechanisms. Up to 5.8 MW of ICRF heating has been coupled into D-T plasmas. The addition of 5.5 MW of ICRF heating to a D-T supershot resulted in an increase in central ion temperature from 26 to 36 keV and an increase in central electron temperature from 8 to 10.5 keV. Up to 80% of the absorbed ICRF power was coupled directly to ions, in good agreement with computer code predictions. These results extrapolate to efficient T heating in future devices such as ITER.
机译:在托卡马克聚变测试反应堆(TFTR)上进行了在离子回旋加速器频率范围(ICRF)内加热D-T等离子体的第一个实验。这些实验有两个主要目标:研究ICRF加热的D-T等离子体的RF物理特性并增强D-T放电的性能。已经在43 MHz下进行了异相电流带激励实验,以探究n_T / n_e浓度高达约40%。在这些实验中,n_T / n_e受碳壁中D再循环的限制。通过改变环形磁场来改变T共振的位置,并调制RF功率(f_(mod)= 5-10 Hz)以阐明竞争性的加热机制。高达5.8 MW的ICRF加热已耦合到D-T等离子体中。将5.5 MW的ICRF加热添加到D-T超级射束中,导致中心离子温度从26 keV升高到36 keV,并且中心电子温度从8 keV升高到10.5 keV。高达80%的吸收ICRF功率直接耦合到离子,与计算机代码预测非常吻合。这些结果可推断出未来的设备(例如ITER)中的高效T加热。

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