Pub Date : 2024-07-18DOI: 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。
{"title":"Corrigendum: Tritium burn efficiency in deuterium–tritium magnetic fusion (2023 Nucl. Fusion 63 126019)","authors":"D.G. Whyte, R. Delaporte-Mathurin, S.E. Ferry and S. Meschini","doi":"10.1088/1741-4326/ad6337","DOIUrl":"https://doi.org/10.1088/1741-4326/ad6337","url":null,"abstract":"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.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"21 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141742517","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}
Pub Date : 2024-07-17DOI: 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.
{"title":"Isotope effects and Alfvén eigenmode stability in JET H, D, T, DT, and He plasmas","authors":"R.A. Tinguely, P.G. Puglia, S. Dowson, M. Porkolab, D. Douai, A. Fasoli, L. Frassinetti, D. King, P. Schneider and JET Contributors","doi":"10.1088/1741-4326/ad6013","DOIUrl":"https://doi.org/10.1088/1741-4326/ad6013","url":null,"abstract":"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.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"60 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141742519","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}
Pub Date : 2024-07-16DOI: 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。
{"title":"High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas","authors":"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","doi":"10.1088/1741-4326/ad5f41","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5f41","url":null,"abstract":"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.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"20 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141718884","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}
Pub Date : 2024-07-10DOI: 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。
{"title":"Impurity transport study based on measurement of visible wavelength high-n charge exchange transitions at W7-X","authors":"Colin Swee, Benedikt Geiger, Oliver Ford, Mark Nornberg, Martin O’Mullane, Peter Poloskei, Felix Reimold, Thilo Romba, Thomas Wegner and the W7-X Team","doi":"10.1088/1741-4326/ad5aad","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5aad","url":null,"abstract":"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.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"41 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141588520","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}
Pub Date : 2024-07-10DOI: 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.
{"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}
Pub Date : 2024-07-09DOI: 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。
{"title":"Interfaces enhanced plasma irradiation resistance in CrMoTaWV/W multilayer films through blocking He diffusion","authors":"Chenyi Qu, Mengqing Hong, Guo Wei, Wentao Ge, Enkai Guo, Fen Zhong, Guangxu Cai, Yongqiang Wang and Feng Ren","doi":"10.1088/1741-4326/ad5aaf","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5aaf","url":null,"abstract":"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.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"47 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141569215","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}
Pub Date : 2024-07-09DOI: 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>