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Corrigendum: Tritium burn efficiency in deuterium–tritium magnetic fusion (2023 Nucl. Fusion 63 126019) 更正:氘氚磁聚变中的氚燃烧效率(2023 Nucl.)
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-18 DOI: 10.1088/1741-4326/ad6337
D.G. Whyte, R. Delaporte-Mathurin, S.E. Ferry and S. Meschini
The controlling parameters regarding tritium burn efficiency (TBE) are derived from first principles and shown to depend fundamentally on the permitted He gas fraction in the divertor and effective pumping speeds of He ash and unburned hydrogenic fuel. The analysis is generic to any equilibrated magnet fusion plasma using a divertor for particle exhaust. The He gas fraction in the plasma limits the maximum TBE due to the link between ash dilution effects in the core plasma and fusion performance. High TBE in magnetic fusion devices is counter-correlated to achieving high gain and power density for commercial fusion. The impact of TBE on fusion performance for several figures of merit are derived, including power density, required product, and plasma energy gain . The TBE formulation presented here is applied to existing devices, based on published data of enrichment and from research tokamaks. This assessment strongly motivates exploration of technologies that would enhance the effective pumping speed of He to fuel out of the plasma.
有关氚燃烧效率(TBE)的控制参数是根据第一原理推导出来的,并表明这些参数主要取决于分流器中允许的氦气分量以及氦灰和未燃烧氢燃料的有效抽速。该分析适用于任何使用分流器排出粒子的平衡磁核聚变等离子体。由于核心等离子体中的灰稀释效应与聚变性能之间存在联系,等离子体中的 He 气体组分限制了最大 TBE。磁核聚变装置中的高 TBE 与实现商业核聚变的高增益和高功率密度是背道而驰的。本文得出了 TBE 对核聚变性能的影响,包括功率密度、所需乘积和等离子体能量增益。根据已公布的富集数据和研究托卡马克的数据,本文提出的 TBE 方案适用于现有装置。这一评估有力地推动了对能够提高等离子体中氦到燃料的有效泵送速度的技术的探索。
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引用次数: 0
Isotope effects and Alfvén eigenmode stability in JET H, D, T, DT, and He plasmas JET H、D、T、DT 和 He 等离子体中的同位素效应和阿尔芬特征模式稳定性
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-17 DOI: 10.1088/1741-4326/ad6013
R.A. Tinguely, P.G. Puglia, S. Dowson, M. Porkolab, D. Douai, A. Fasoli, L. Frassinetti, D. King, P. Schneider and JET Contributors
While much about Alfvén eigenmode (AE) stability has been explored in previous and current tokamaks, open questions remain for future burning plasma experiments, especially regarding exact stability threshold conditions and related isotope effects; the latter, of course, requiring good knowledge of the plasma ion composition. In the JET tokamak, eight in-vessel antennas actively excite stable AEs, from which their frequencies, toroidal mode numbers, and net damping rates are assessed. The effective ion mass can also be inferred using measurements of the plasma density and magnetic geometry. Thousands of AE stability measurements have been collected by the Alfvén Eigenmode Active Diagnostic in hundreds of JET plasmas during the recent Hydrogen, Deuterium, Tritium, DT, and Helium-4 campaigns. In this novel AE stability database, spanning all four main ion species, damping is observed to decrease with increasing Hydrogenic mass, but increase for Helium, a trend consistent with radiative damping as the dominant damping mechanism. These data are important for confident predictions of AE stability in both non-nuclear (H/He) and nuclear (D/T) operations in future devices. In particular, if radiative damping plays a significant role in overall stability, some AEs could be more easily destabilized in D/T plasmas than their H/He reference pulses, even before considering fast ion and alpha particle drive. Active MHD spectroscopy is also employed on select HD, HT, and DT plasmas to infer the effective ion mass, thereby closing the loop on isotope analysis and demonstrating a complementary method to typical diagnosis of the isotope ratio.
虽然在以前和当前的托卡马克中已经探索了很多关于阿尔芬特征模(AE)稳定性的问题,但对于未来的燃烧等离子体实验来说,仍有很多问题有待解决,特别是关于确切的稳定性阈值条件和相关的同位素效应;当然,后者需要很好地了解等离子体的离子组成。在 JET 托卡马克中,八个腔内天线主动激发稳定的 AE,并从中评估其频率、环模数和净阻尼率。通过测量等离子体密度和磁性几何形状,还可以推断出有效离子质量。在最近的氢、氘、氚、DT 和氦-4 活动中,阿尔文特征模式主动诊断仪在数百个 JET 等离子体中收集了数千次 AE 稳定性测量结果。在这个涵盖所有四种主要离子的新型 AE 稳定性数据库中,可以观察到阻尼随氢质量的增加而减小,但氦质量的增加而增大,这一趋势与辐射阻尼作为主要阻尼机制是一致的。这些数据对于预测未来装置在非核(氢/氦)和核(D/T)运行中的 AE 稳定性非常重要。特别是,如果辐射阻尼在整体稳定性中起着重要作用,那么即使在考虑快速离子和阿尔法粒子驱动之前,某些 AE 在 D/T 等离子体中可能比其 H/He 参考脉冲更容易失稳。在选定的 HD、HT 和 DT 等离子体中还采用了主动 MHD 光谱法来推断有效离子质量,从而结束了同位素分析的循环,并展示了典型同位素比诊断的补充方法。
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引用次数: 0
High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas 负三角形 DIII-D 等离子体中无 H 模式边缘时的高性能功率处理
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-16 DOI: 10.1088/1741-4326/ad5f41
F. Scotti, A. Marinoni, A.G. McLean, C. Paz-Soldan, K.E. Thome, M. Zhao, S. Allen, M. Austin, M.G. Burke, D. Eldon, M. Fenstermacher, A. Hyatt, C.J. Lasnier, A. Leonard, J. Lore, A.O. Nelson, T. Osborne, O. Sauter, D. Truong, M.A. Van Zeeland, H.Q. Wang and R. Wilcox
Experiments performed during strongly-shaped high-power diverted negative triangularity (NT) experiments in DIII-D achieved detached divertor conditions and a transient-free edge, showcasing the potential for application of NT to a core-edge integrated reactor-like scenario and providing the first characterization of the parametric dependencies for detachment onset. Detached divertor conditions will be required in future devices to mitigate divertor heat fluxes. Access to dissipative divertor conditions was investigated via an increase in upstream density. Detachment onset at the outer strike point was achieved with H-mode level confinement and reactor-relevant normalized pressures . Confinement degradation was observed with deeper detachment, associated with the loss of an electron temperature pedestal. Differences in geometry, radial transport, impact of cross field drifts are discussed to explain differences in access to detachment in NT discharges. Higher normalized densities, with respect to equivalent discharges in positive triangularity, were necessary to achieve detachment, partially explained by the shorter parallel connection length to the targets. The effect of cross-field particle drifts (E×B, B B) on access to detachment was demonstrated by the lower upstream density needed to access detachment with ion B B drift directed outside of the active divertor (Greenwald fraction 0.9–1.0 vs 1.3). The upstream density at detachment onset was observed to increase linearly with plasma current with ion B B drift into the divertor, consistent with the observed narrowing of the scrape-off layer heat flux width λq. Edge fluid simulations capture separatrix densities needed to achieve detachment in NT plasma and their dependence on drift direction. The ability to reproduce detachment dynamics in NT plasma increases the confidence in future design studies for NT divertors.
在 DIII-D 强形高功率分流负三角形(NT)实验中进行的实验实现了脱离岔道条件和无瞬态边缘,展示了将 NT 应用于类似堆芯边缘集成反应堆方案的潜力,并首次描述了脱离开始的参数依赖性。未来的装置将需要分离岔流条件,以减轻岔流热通量。通过增加上游密度,对进入耗散岔流条件进行了研究。外侧撞击点的脱离是在 H 模式水平约束和反应堆相关归一化压力下实现的。在更深的脱离过程中观察到了与电子温度基座丧失有关的约束退化。讨论了几何形状的差异、径向传输、交叉场漂移的影响,以解释 NT 放电中脱离通道的差异。与正三角形的等效放电相比,需要更高的归一化密度才能实现脱离,与目标的平行连接长度较短是部分原因。跨场粒子漂移(E×B、B B)对脱离的影响表现在,离子 B B 漂移指向主动分流器外时,脱离所需的上游密度较低(格林沃德分数 0.9-1.0 与 1.3)。观察到脱离开始时的上游密度随离子 B B 漂移进入分流器时等离子体电流的增加而线性增加,这与观察到的刮离层热通量宽度 λq 变窄一致。边缘流体模拟捕捉了在 NT 等离子体中实现脱离所需的分离矩阵密度及其对漂移方向的依赖性。再现 NT 等离子体中分离动力学的能力增强了未来 NT 分流器设计研究的信心。
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引用次数: 0
Impurity transport study based on measurement of visible wavelength high-n charge exchange transitions at W7-X 基于 W7-X 可见光波长高 n 电荷交换跃迁测量的杂质传输研究
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-10 DOI: 10.1088/1741-4326/ad5aad
Colin Swee, Benedikt Geiger, Oliver Ford, Mark Nornberg, Martin O’Mullane, Peter Poloskei, Felix Reimold, Thilo Romba, Thomas Wegner and the W7-X Team
A recently installed high-speed charge exchange diagnostic at the W7-X stellarator has been used to identify several high-n Rydberg emission lines near 500 nm following impurity injections. The wavelengths of observed high-n Rydberg transitions are independent of the impurity species and originate from ions with ionization states ranging from 14+ to 45+ suggesting that this approach can be applied to a variety of heavy impurities. Moreover, little to no passive signal is observed since the high-n energy levels are unlikely to be populated by electron impact excitation. The combination of the newly developed diagnostic and the observation of high-n Rydberg states provides spatially resolved, high-speed measurements of multiple charge states which are analyzed in a Bayesian inference framework to determine both impurity diffusion and convection profiles. Measurements from the 2023 experimental campaign conclusively show high diffusion and an inward pinch in the core, well above predictions by neoclassical theory.
最近在 W7-X 恒星器上安装的高速电荷交换诊断仪被用来识别杂质注入后 500 nm 附近的几条高 n Rydberg 发射线。观测到的高 n Rydberg 转变的波长与杂质种类无关,并且来自电离状态从 14+ 到 45+ 的离子,这表明这种方法可用于各种重杂质。此外,由于高 n 能级不太可能被电子撞击激发填充,因此几乎观察不到被动信号。新开发的诊断方法与对高 n Rydberg 状态的观测相结合,提供了对多种电荷状态的空间分辨高速测量,并在贝叶斯推理框架下进行分析,以确定杂质扩散和对流剖面。2023 年实验活动的测量结果确凿地显示了核心的高扩散和向内挤压,远高于新古典理论的预测。
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引用次数: 0
Observation of alpha-particles in recent D–T experiments on JET 最近在 JET 上进行的 D-T 实验中观测到的α粒子
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-10 DOI: 10.1088/1741-4326/ad5c81
V.G. Kiptily, C.D. Challis, R. Dumont, M. Fitzgerald, J. Garcia, L. Garzotti, Z. Ghani, J. Hobirk, P. Jacquet, A. Kappatou, D. Keeling, Ye. Kazakov, P. Mantica, M.J. Mantsinen, S.E. Sharapov, E.R. Solano, D. Van Eester, P.J. Bonofiglo, T. Craciunescu, A. Dal Molin, J. Eriksson, V. Goloborodko, M.V. Iliasova, E.M. Khilkevitch, D. King, I. Lengar, M. Nocente, S. Menmuir, M. Podestà, M. Poradzinski, D. Rigamonti, J. Rivero-Rodriguez, Z. Stancar, A.E. Shevelev, P. Siren, H. Sun, D.M. Taylor, M. Tardocchi, P. Beaumont, F. Belli, F.E. Cecil, R. Coelho, M. Curuia, M. Garcia-Munoz, E. Joffrin, C. Lowry, M. Lennholm, E. Lerche, C.F. Maggi, J. Mailloux, D. Marocco, M. Maslov, C. Perez Von Thun, F. Rimini, V. Zoita and JET Contributors
The fusion reaction between deuterium and tritium, D(T,n)4He is the main source of energy in future thermonuclear reactors. Alpha-particles (4He-ions) born with an average energy of 3.5 MeV transferring energy to the thermal plasma during their slowing down, should provide the self-sustained D–T plasma burn. The adequate confinement of α-particles is essential to provide efficient heating of the bulk plasma and steady burning of a reactor plasma. That is why the fusion-born α-particle studies have been a priority task in the second D–T experiments (DTE2) on the Joint European Torus (JET) to understand the main mechanisms of their slowing down, redistribution and losses and to develop optimal plasma scenarios. JET with Be-wall and W-divertor, enhanced auxiliary heating systems and improved energetic-particle diagnostic capabilities, producing significant population of α-particles, provided the possibility for comprehensive studying of the α-particle behaviour. Selected results of the confined and lost α-particle measurements, evidence of α-particle self-heating and assessments of the fusion performance are presented in this paper giving an opportunity for further modelling and extrapolation to the International Thermonuclear Experimental Reactor and burning plasma reactors.
氘和氚之间的聚变反应(D(T,n)4He)是未来热核反应堆的主要能量来源。平均能量为 3.5 MeV 的α粒子(4He 离子)在减速过程中将能量传递给热等离子体,从而提供自我维持的 D-T 等离子体燃烧。α粒子的充分约束对于有效加热大块等离子体和反应堆等离子体的稳定燃烧至关重要。因此,在欧洲联合环(JET)上进行的第二次 D-T 实验(DTE2)中,聚变产生的 α 粒子研究是一项优先任务,目的是了解其减速、再分布和损耗的主要机制,并制定最佳等离子体方案。JET 配备了 Be-wall 和 W-divertor,增强了辅助加热系统,提高了高能粒子诊断能力,产生了大量 α 粒子,为全面研究 α 粒子行为提供了可能。本文介绍了α粒子封闭和丢失测量的部分结果、α粒子自热的证据以及聚变性能评估,为进一步建模和推断国际热核实验反应堆和燃烧等离子反应堆提供了机会。
{"title":"Observation of alpha-particles in recent D–T experiments on JET","authors":"V.G. Kiptily, C.D. Challis, R. Dumont, M. Fitzgerald, J. Garcia, L. Garzotti, Z. Ghani, J. Hobirk, P. Jacquet, A. Kappatou, D. Keeling, Ye. Kazakov, P. Mantica, M.J. Mantsinen, S.E. Sharapov, E.R. Solano, D. Van Eester, P.J. Bonofiglo, T. Craciunescu, A. Dal Molin, J. Eriksson, V. Goloborodko, M.V. Iliasova, E.M. Khilkevitch, D. King, I. Lengar, M. Nocente, S. Menmuir, M. Podestà, M. Poradzinski, D. Rigamonti, J. Rivero-Rodriguez, Z. Stancar, A.E. Shevelev, P. Siren, H. Sun, D.M. Taylor, M. Tardocchi, P. Beaumont, F. Belli, F.E. Cecil, R. Coelho, M. Curuia, M. Garcia-Munoz, E. Joffrin, C. Lowry, M. Lennholm, E. Lerche, C.F. Maggi, J. Mailloux, D. Marocco, M. Maslov, C. Perez Von Thun, F. Rimini, V. Zoita and JET Contributors","doi":"10.1088/1741-4326/ad5c81","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5c81","url":null,"abstract":"The fusion reaction between deuterium and tritium, D(T,n)4He is the main source of energy in future thermonuclear reactors. Alpha-particles (4He-ions) born with an average energy of 3.5 MeV transferring energy to the thermal plasma during their slowing down, should provide the self-sustained D–T plasma burn. The adequate confinement of α-particles is essential to provide efficient heating of the bulk plasma and steady burning of a reactor plasma. That is why the fusion-born α-particle studies have been a priority task in the second D–T experiments (DTE2) on the Joint European Torus (JET) to understand the main mechanisms of their slowing down, redistribution and losses and to develop optimal plasma scenarios. JET with Be-wall and W-divertor, enhanced auxiliary heating systems and improved energetic-particle diagnostic capabilities, producing significant population of α-particles, provided the possibility for comprehensive studying of the α-particle behaviour. Selected results of the confined and lost α-particle measurements, evidence of α-particle self-heating and assessments of the fusion performance are presented in this paper giving an opportunity for further modelling and extrapolation to the International Thermonuclear Experimental Reactor and burning plasma reactors.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"8 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141586723","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Interfaces enhanced plasma irradiation resistance in CrMoTaWV/W multilayer films through blocking He diffusion 通过阻断 He 扩散增强 CrMoTaWV/W 多层薄膜的抗等离子辐照能力
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-09 DOI: 10.1088/1741-4326/ad5aaf
Chenyi Qu, Mengqing Hong, Guo Wei, Wentao Ge, Enkai Guo, Fen Zhong, Guangxu Cai, Yongqiang Wang and Feng Ren
The performance of plasma-facing materials (PFMs) is one of the key factors that significantly impact the stability of operation in fusion reactors. Herein, a new CrMoTaWV/W (high entropy alloy (HEA)/W) multilayer structure is designed as PFM to investigate its resistance to He plasma irradiation. It was observed that the introduction of the interfaces effectively absorbed plenty of He atoms, preventing them from diffusing into the material and delaying the formation of fuzz incubation zone, therefore, enhancing the resistance to plasma irradiation. The thickness transformed to fuzz in the HEA/W multilayer films was observed to be about two-thirds of those in the CrMoTaWV (HEA) film. Additionally, the fuzz growth rates in HEA/W multilayer films are lower than the average growth rate of bulk W and HEA films combined. These findings highlight a promising new avenue for the exploration of high-performance PFMs.
面向等离子体的材料(PFM)的性能是严重影响聚变反应堆运行稳定性的关键因素之一。本文设计了一种新型 CrMoTaWV/W(高熵合金 (HEA)/W) 多层结构作为 PFM,以研究其抗 He 等离子体辐照的性能。结果表明,界面的引入有效地吸收了大量 He 原子,阻止了它们向材料内部的扩散,延缓了模糊孕育区的形成,从而增强了抗等离子辐照的能力。据观察,HEA/W 多层薄膜中转变为毛刺的厚度约为 CrMoTaWV(HEA)薄膜的三分之二。此外,HEA/W 多层薄膜中绒毛的生长率低于 W 和 HEA 薄膜的平均生长率之和。这些发现为探索高性能 PFM 指明了一条大有可为的新途径。
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引用次数: 0
Turbulence link to L-mode, I-mode, and H-mode confinement in the DIII-D tokamak 湍流与 DIII-D 托卡马克中的 L 模、I 模和 H 模约束的联系
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-09 DOI: 10.1088/1741-4326/ad5aae
J. Chen, D.L. Brower, J. McClenaghan, Z. Yan, A.E. Hubbard, R. Groebner
Understanding the physics of low-confinement (L-), improved-confinement (I-), and high-confinement (H-) modes is critical for fusion reactors. The finding herein reports observations of two types of turbulence coexisting near the L-mode edge, one magnetohydrodynamic (MHD)-like and another micro-tearing mode (MTM)-like, linked to the H-mode and I-mode confinement in the DIII-D tokamak. Ion-scale magnetic and density turbulence is measured using a Faraday-effect radial-interferometer-polarimeter and beam-emission-spectroscopy (BES). Broadband turbulence spectra of up to ∼600 kHz are observed in two discharges where transitions between L-mode, I-mode, and H-mode occurs. Turbulence is found to be inversely correlated with confinement, meaning lower turbulence power at higher confinement. Distinctively, the high-frequency (HF, >∼100 kHz) magnetic turbulence power changes by the most (55%) during transitions primarily involving energy confinement change, whereas the low-frequency (LF, <∼100 kHz) magnetic and density turbulence power changes by the most (80%) during transitions primarily involving particle confinement change. The LF turbulence amplitude oscillates with and leads to deuterium-alpha emission oscillations before an H-mode. These results imply that HF turbulence mainly affects energy confinement whereas LF turbulence can affect particle confinement. The magnetic and density turbulence exhibits coherence up to 0.6 and cross-phase magnitude close to <inline-formula><tex-math><?CDATA $pi /2$?></tex-math><mml:math overflow="scroll"><mml:mrow><mml:mi>π</mml:mi><mml:mrow><mml:mo>/</mml:mo></mml:mrow><mml:mn>2</mml:mn></mml:mrow></mml:math><inline-graphic xlink:href="nfad5aaeieqn1.gif" xlink:type="simple"></inline-graphic></inline-formula> in most cases, suggesting they have a common origin in both the LF and HF ranges. BES suggests that LF turbulence resides at the edge (<inline-formula><tex-math><?CDATA $rho = 0.95$?></tex-math><mml:math overflow="scroll"><mml:mrow><mml:mi>ρ</mml:mi><mml:mo>=</mml:mo><mml:mn>0.95</mml:mn></mml:mrow></mml:math><inline-graphic xlink:href="nfad5aaeieqn2.gif" xlink:type="simple"></inline-graphic></inline-formula>) and HF turbulence can be at the outer core (<inline-formula><tex-math><?CDATA $rho = 0.8$?></tex-math><mml:math overflow="scroll"><mml:mrow><mml:mi>ρ</mml:mi><mml:mo>=</mml:mo><mml:mn>0.8</mml:mn></mml:mrow></mml:math><inline-graphic xlink:href="nfad5aaeieqn3.gif" xlink:type="simple"></inline-graphic></inline-formula>) or edge (<inline-formula><tex-math><?CDATA $rho = 0.95$?></tex-math><mml:math overflow="scroll"><mml:mrow><mml:mi>ρ</mml:mi><mml:mo>=</mml:mo><mml:mn>0.95</mml:mn></mml:mrow></mml:math><inline-graphic xlink:href="nfad5aaeieqn4.gif" xlink:type="simple"></inline-graphic></inline-formula>). Comparisons of measurements, theory, and gyrokinetic simulations suggest that HF turbulence is MTM-like in all cases, whereas LF turbulence is more consistent with MHD-like modes and th
了解低约束(L-)、改进约束(I-)和高约束(H-)模式的物理特性对聚变反应堆至关重要。本文的发现报告了对 L 模式边缘附近共存的两种湍流的观测,一种类似于磁流体动力(MHD),另一种类似于微撕裂模式(MTM),与 DIII-D 托卡马克中的 H 模式和 I 模式约束有关。离子尺度的磁湍流和密度湍流是利用法拉第效应径向干涉仪-偏振仪和光束发射光谱仪(BES)测量的。在两个发生 L 模式、I 模式和 H 模式转换的放电中观测到了高达 ∼600 kHz 的宽带湍流频谱。发现湍流与约束成反比,即约束越高,湍流功率越低。不同的是,高频(HF,>∼100 kHz)磁湍流功率在主要涉及能量束缚变化的过渡期间变化最大(55%),而低频(LF,<∼100 kHz)磁湍流和密度湍流功率在主要涉及粒子束缚变化的过渡期间变化最大(80%)。低频湍流振幅与 H 模式之前的氘-α 辐射振荡同步,并导致 H 模式之前的氘-α 辐射振荡。这些结果表明,高频湍流主要影响能量约束,而低频湍流会影响粒子约束。在大多数情况下,磁湍流和密度湍流表现出高达 0.6 的相干性和接近 π/2 的跨相幅度,这表明它们在低频和高频范围内具有共同的起源。BES 表明低频湍流位于边缘(ρ=0.95),而高频湍流可能位于外核(ρ=0.8)或边缘(ρ=0.95)。对测量结果、理论和陀螺动力学模拟的比较表明,高频湍流在所有情况下都类似于 MTM,而低频湍流则更符合类似于 MHD 的模式,而且在转换过程中,确切的不稳定性可能会发生变化--除了在低碰撞度的 H 模式中可能存在漂移波起源。这些结果表明,H 模式涉及被抑制的 MHD 类湍流,而 I 模式则减轻了 MTM 类湍流以及基本不变的 MHD 类湍流。
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引用次数: 0
Hybrid model predictive control techniques for safety factor profile and stored energy regulation while incorporating NBI constraints 用于安全系数曲线和储能调节的混合模型预测控制技术,同时纳入 NBI 约束条件
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-08 DOI: 10.1088/1741-4326/ad5c7f
Brian Leard, Zibo Wang, Sai Tej Paruchuri, Eugenio Schuster, Tariq Rafiq
A novel hybrid Model Predictive Control (MPC) algorithm has been designed for simultaneous safety factor (q) profile and stored energy (w) control while incorporating the pulse-width-modulation constraints associated with the neutral beam injection (NBI) system. Regulation of the q-profile has been extensively shown to be a key factor for improved confinement as well as non-inductive sustainment of the plasma current. Simultaneous control of w is necessary to prevent the triggering of pressure-driven magnetohydrodynamic instabilities as the controller shapes the q profile. Conventional MPC schemes proposed for q-profile control have considered the NBI powers as continuous-time signals, ignoring the discrete-time nature of these actuators and leading in some cases to performance loss. The hybrid MPC scheme in this work has the capability of incorporating the discrete-time actuator dynamics as additional constraints. In nonlinear simulations, the proposed hybrid MPC scheme demonstrates improved q-profile+w control performance for NSTX-U operating scenarios.
我们设计了一种新颖的混合模型预测控制(MPC)算法,用于同时控制安全系数(q)曲线和储能(w),同时纳入与中性束注入(NBI)系统相关的脉宽调制约束。q曲线的调节已被广泛证明是改善等离子体电流约束和非感应维持的关键因素。在控制器调节 q 曲线时,有必要同时控制 w,以防止引发压力驱动的磁流体力学不稳定性。针对 q 曲线控制提出的传统 MPC 方案将 NBI 功率视为连续时间信号,忽略了这些执行器的离散时间性质,在某些情况下会导致性能损失。本研究中的混合 MPC 方案能够将离散时间致动器动力学作为附加约束纳入其中。在非线性仿真中,所提出的混合 MPC 方案在 NSTX-U 运行情况下显示出更好的 q-profile+w 控制性能。
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引用次数: 0
Real-time plasma equilibrium reconstruction and shape control for the MAST Upgrade tokamak MAST 升级型托卡马克的实时等离子体平衡重建和形状控制
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-08 DOI: 10.1088/1741-4326/ad5c80
H. Anand, W. Wehner, D. Eldon, A. Welander, Z. Xing, A. Lvovskiy, J. Barr, E. Cho, B. Sammuli, D. Humphreys, N. Eidietis, A. Leonard, M. Kochan, C. Vincent, G. McArdle, G. Cunningham, A. Thornton, J. Harrison, V. Soukhanovskii, J. Lovell
Real-time magnetic control has been developed to deliver precise control of multiple plasma shape parameters for advanced divertor configurations, including double-null, Super-X, X-point target and X-divertor for the first time on the MAST Upgrade (MAST-U) spherical tokamak. Successful real-time magnetic equilibrium control of different plasma shape variables has been accomplished in the 2022–2023 MAST-U experimental campaign for the advanced MAST-U divertor configurations. Application of the MAST-U boundary reconstruction algorithm, LEMUR, is described and compared with off-line equilibrium reconstruction and diagnostic measurements. The process of design and verification of the axisymmetric magnetic control schemes using a suite of control analysis tools (known collectively as TokSys) is also described.
已开发出实时磁控制功能,可为先进的分流器配置提供多个等离子体形状参数的精确控制,包括双空、Super-X、X 点目标和 X 分流器,这在 MAST 升级(MAST-U)球形托卡马克上尚属首次。在2022-2023年MAST-U实验活动中,针对先进的MAST-U分流器配置,成功实现了对不同等离子体形状变量的实时磁平衡控制。介绍了MAST-U边界重建算法LEMUR的应用,并与离线平衡重建和诊断测量进行了比较。还介绍了使用一套控制分析工具(统称为 TokSys)设计和验证轴对称磁控制方案的过程。
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引用次数: 0
Numerical modelling of sawteeth and sawtooth-free regime 锯齿和无锯齿系统的数值建模
IF 3.3 1区 物理与天体物理 Q1 PHYSICS, FLUIDS & PLASMAS Pub Date : 2024-07-08 DOI: 10.1088/1741-4326/ad5c7e
Q. Yu, S. Günter, K. Lackner
To better understand the sawteeth physics and the sawtooth-free regime associated with the hybrid scenario in tokamak experiments, numerical calculations up to quasi-steady state have been carried out for realistic middle-size tokamak plasma parameters, including the bootstrap current perturbation and basing on both the single- and two-fluid equations with the large aspect ratio approximation. Two types of the sawtooth crash are found in multiple sawteeth simulations: (1) For a low equilibrium bootstrap current fraction, the crash is caused by the internal kink mode, as expected; (2) When the bootstrap current density fraction is larger than 10% in the core region, however, the crash is caused by the non-ideal double kink mode, in contrary to the conventional understanding. In this case, a non-monotonic radial profile of the safety factor q with two q=1 surfaces emerges before the crash, caused by the bootstrap current density and plasma resistivity perturbations, although the original equilibrium has only single q = 1 surface. In both types of sawtooth crashes, the crash time in two-fluid simulations is tens of microseconds, as observed in experiments. Furthermore, for a relatively low ion density and finite bootstrap current density fraction, a transition from the sawtooth to the sawtooth-free regime is found, in which flat q profiles with the q value being about unity in the central region, similar to that observed in hybrid scenario experiments, are maintained by the dynamo effect. To enter into the sawtooth-free regime in two-fluid simulations, a much larger Alfvén velocity than that in single-fluid simulations is required due to the diamagnetic drift.
为了更好地理解与托卡马克实验中混合情形相关的锯齿物理和无锯齿机制,我们针对现实的中等尺寸托卡马克等离子体参数,包括自举电流扰动,并基于大纵横比近似的单流体和双流体方程,进行了直至准稳态的数值计算。在多锯齿模拟中发现了两种类型的锯齿碰撞:(1)当平衡自举电流分数较低时,碰撞是由内部扭结模式引起的,正如所预期的那样;(2)然而,当自举电流密度分数在核心区域大于 10%时,碰撞是由非理想的双扭结模式引起的,这与传统的理解相反。在这种情况下,安全系数 q 的非单调径向轮廓在撞击前出现了两个 q=1 的面,这是由自举电流密度和等离子体电阻率扰动引起的,尽管原来的平衡状态只有一个 q=1 的面。在这两种类型的锯齿碰撞中,双流体模拟的碰撞时间都是几十微秒,与实验中观察到的一样。此外,在相对较低的离子密度和有限的自举电流密度分数条件下,会发现从锯齿向无锯齿状态的过渡,在这一状态下,q 值在中心区域约为 1 的平坦 q 曲线在动力效应的作用下得以维持,这与混合情景实验中观察到的情况类似。在双流体模拟中,要进入无锯齿状态,由于二磁漂移,需要比单流体模拟大得多的阿尔费芬速度。
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引用次数: 0
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Nuclear Fusion
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