N. Wendler , A. Chomiczewska , W. Gromelski , E. Kowalska-Strzęciwilk , G. Telesca , I. Ivanova–Stanik , L. Garzotti , D. Van Eester , V.K. Zotta , D. Frigione , F. Rimini , G. Pucella , JET Contributors , The Eurofusion Tokamak Exploitation Team
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The first one, so-called baseline scenario is relying on high plasma current (I<sub>p</sub>≈3.5 MA), normalized beta β<sub>N</sub> < 2 and safety factor q<sub>95</sub> ≈ 3 (Garzotti et al., 2023). On the other hand, the second one, so-called Hybrid scenario is operating at lower plasma current (flat-top I<sub>p</sub> ≤ 2.6 MA) and density with respect to the baseline, higher normalized beta β<sub>N</sub> > 2 and safety factor q<sub>95</sub> ≈ 4.8 (Hobirk et al., 2023).</div><div>In this paper we focus on the impurity behaviour analysis for the baseline discharges at I<sub>p</sub> = 3.5 MA and B<sub>T</sub> = 3.3 T with D, T and DT plasmas, in which the gas and power waveform were optimized to achieve the best possible performance. In particular, we study the impact of total heating power (P<sub>tot</sub> + P<sub>alpha</sub>), flat-top gas flow and ELM (edge localized modes) frequency on mid-Z (Nickel (Ni), Copper (Cu)) and high-Z (Tungsten (W)) impurities. 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引用次数: 0
摘要
为了支持未来的热核聚变实验堆运行,在欧洲联合环形器(JET)上进行了纯氘(D)、氚(T)和氘氚(D-T)的类似热核聚变实验堆壁(钨分流器和铍主室)的实验活动。近年来最重要的挑战之一是开发两种主要方案,研究实现高聚变功率和良好等离子体约束的不同方法(Garzotti 等人,2023 年)。第一个方案,即所谓的基线方案,依赖于高等离子体电流(Ip≈3.5 MA)、归一化贝塔βN <2和安全系数q95≈3(Garzotti等人,2023年)。另一方面,第二个方案,即所谓的混合方案,相对于基线,在较低的等离子体电流(平顶 Ip ≤ 2.6 MA)和密度下运行,归一化贝塔系数 βN > 2 和安全系数 q95 ≈ 4.8(Hobirk 等人,2023 年)、在本文中,我们重点分析了在 Ip = 3.5 MA 和 BT = 3.3 T 条件下,使用 D、T 和 DT 等离子体进行基线放电时的杂质行为。我们特别研究了总加热功率(Ptot + Palpha)、平顶气体流量和 ELM(边缘局部模式)频率对中 Z(镍(Ni)、铜(Cu))和高 Z(钨(W))杂质的影响。此外,我们还比较了基准方案(Ip = 3.5MA,BT = 3.3 T,Pin ≈ 35 MW)中 D 和 DT 两种性能最好的脉冲,以确定导致 DT 脉冲期间辐射增加、等离子体提前终止的原因。所有展示的结果都依赖于紫外辐射计和螺栓测量系统收集的数据。详细分析表明,在基线情况下,与 D 相比,T 和 DT 等离子体的辐射较高,这很可能是由于钨(W)造成的。此外,对于两个性能最好的基线脉冲,层析重构显示辐射功率密度主要从等离子体的低场侧(LFS)发射,W 并未在等离子体中心聚集(Telesca 等人,2024 年)。
Impurity behaviour in JET high-current baseline scenario for Deuterium, Tritium and Deuterium-Tritium plasmas
To support future ITER operation, experimental campaigns at the Joint European Torus (JET) with an ITER-like wall (tungsten divertor and beryllium main chamber) in pure deuterium (D), tritium (T) and Deuterium-Tritium (D-T) were performed. One of the most important challenges in recent years was the development of two main scenarios that investigated different approaches to achieve the high fusion power as well as good plasma confinement (Garzotti et al., 2023). The first one, so-called baseline scenario is relying on high plasma current (Ip≈3.5 MA), normalized beta βN < 2 and safety factor q95 ≈ 3 (Garzotti et al., 2023). On the other hand, the second one, so-called Hybrid scenario is operating at lower plasma current (flat-top Ip ≤ 2.6 MA) and density with respect to the baseline, higher normalized beta βN > 2 and safety factor q95 ≈ 4.8 (Hobirk et al., 2023).
In this paper we focus on the impurity behaviour analysis for the baseline discharges at Ip = 3.5 MA and BT = 3.3 T with D, T and DT plasmas, in which the gas and power waveform were optimized to achieve the best possible performance. In particular, we study the impact of total heating power (Ptot + Palpha), flat-top gas flow and ELM (edge localized modes) frequency on mid-Z (Nickel (Ni), Copper (Cu)) and high-Z (Tungsten (W)) impurities. In addition, we compared the two best performing pulses of the baseline scenario (Ip = 3.5MA, BT = 3.3 T and Pin ≈ 35 MW) in D and DT in order to identify the causes responsible for the increase in radiation during the DT pulse, which led to an early plasma termination. All presented results rely on the data collected by the VUV as well as the bolometry system. Detailed analysis indicates that in the baseline scenario, higher radiation, which is most likely due to the tungsten (W), is observed for T and DT plasmas in comparison to D. Moreover, for the two best performing baseline pulses, tomographic reconstructions show that the radiated power density is mainly emitted from the low field side (LFS) of the plasma and W does not accumulate in the plasma center (Telesca et al., 2024).
期刊介绍:
The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.