cometadata/datacite-titles-descriptions-related-identifiers huggingface dataset:
DOI: 10.57760/sciencedb.03652
title: Effects of input power, gas flow rate and hydrogen concentration on Cu film deposition by a radio frequency driven non-thermal atmospheric pressure plasma jet
title: Effects of input power, gas flow rate and hydrogen concentration on Cu film deposition by a radio frequency driven non-thermal atmospheric pressure plasma jet

description: A radio frequency driven non-thermal atmospheric plasma jet with a copper wire used as precursor is applied for Cu fifilm deposition. The effffects of input power, hydrogen concentration (CH2) and gas flflow rate on the discharge parameters, and eventually on fifilm deposition rate and its properties are investigated. The results show that, besides the plasma gas temperature (Tg), the discharge current flflowing through the copper wire (Ifc) is also a key parameter for Cu fifilm deposition. With increasing input power, both Tg and Ifc increase, which both facilitate the increase of fifilm deposition rate, surface roughness and particle size on the fifilm. Higher gas flflow rate leads to lower Tg, and results in the decrease of the deposition rate, surface roughness and particle size. The inflfluences of CH2 in plasma forming gas on Cu fifilm deposition have dual characters, due to the increase in the Tg and decease in the Ifc with CH2 increase. When the CH2 is below1.6‰, increasing CH2 has promotion role on the fifilm deposition rate increase and particle size enlargement on the fifilm, and the results reverse as the CH2 is above 1.6‰.
description: A radio frequency driven non-thermal atmospheric plasma jet with a copper wire used as precursor is applied for Cu fifilm deposition. The effffects of input power, hydrogen concentration (CH2) and gas flflow rate on the discharge parameters, and eventually on fifilm deposition rate and its properties are investigated. The results show that, besides the plasma gas temperature (Tg), the discharge current flflowing through the copper wire (Ifc) is also a key parameter for Cu fifilm deposition. With increasing input power, both Tg and Ifc increase, which both facilitate the increase of fifilm deposition rate, surface roughness and particle size on the fifilm. Higher gas flflow rate leads to lower Tg, and results in the decrease of the deposition rate, surface roughness and particle size. The inflfluences of CH2 in plasma forming gas on Cu fifilm deposition have dual characters, due to the increase in the Tg and decease in the Ifc with CH2 increase. When the CH2 is below1.6‰, increasing CH2 has promotion role on the fifilm deposition rate increase and particle size enlargement on the fifilm, and the results reverse as the CH2 is above 1.6‰.
DOI: 10.57760/sciencedb.03655
title: Effect of lithium coating on long pulse high performance plasma discharges in EAST
title: EAST装置上锂化壁处理对长脉冲高性能等离子体的效果

description: The data of Effect of lithium coating on long pulse high performance plasma discharges in EAST
description: The data of Effect of lithium coating on long pulse high performance plasma discharges in EAST
DOI: 10.57760/sciencedb.03658
title: N2/H2 Non‑thermal Transferred arc Plasma Nitriding Treatment of Stainless Steel at Atmospheric Pressure
title: N2/H2 Non‑thermal Transferred arc Plasma Nitriding Treatment of Stainless Steel at Atmospheric Pressure

description: In the paper, a novel metal surface nitriding method is presented by using an atmospheric pressure non-thermal transferred arc plasma technique. In the N2/H2 plasma nitriding process, the surface of stainless-steel is treated by the arc root, which shows an irregular movement in a circle-like zone with about 5 mm diameter observed by high speed camera. The discharge has characteristics of high voltage and low current, and the gas tempera ture of the arc column plasma is only about 2900 K determined by the diatomic molecule N2+(B2Σu+→X2Σg+) ftting method. It is found that the NH radical production in plasma plays an important role in the nitriding process. The thickness of nitrided layer can reach 60 μm after processing of 120 min under the optimal experimental conditions. The surface hardness of stainless-steel increased from 220 to about 1200 HV0.1 (Vickers hardness under the force of 0.1kg) after plasma treatment. The treating saturation time for stainless steel surface hardness reaching to 1200 HV0.1 is around 9 min.
description: In the paper, a novel metal surface nitriding method is presented by using an atmospheric pressure non-thermal transferred arc plasma technique. In the N2/H2 plasma nitriding process, the surface of stainless-steel is treated by the arc root, which shows an irregular movement in a circle-like zone with about 5 mm diameter observed by high speed camera. The discharge has characteristics of high voltage and low current, and the gas tempera ture of the arc column plasma is only about 2900 K determined by the diatomic molecule N2+(B2Σu+→X2Σg+) ftting method. It is found that the NH radical production in plasma plays an important role in the nitriding process. The thickness of nitrided layer can reach 60 μm after processing of 120 min under the optimal experimental conditions. The surface hardness of stainless-steel increased from 220 to about 1200 HV0.1 (Vickers hardness under the force of 0.1kg) after plasma treatment. The treating saturation time for stainless steel surface hardness reaching to 1200 HV0.1 is around 9 min.
DOI: 10.57760/sciencedb.03666
title: Figure-Experimental response of the divertor particle flux to internal transport barrier dynamics in EAST high-beta(N) discharges
title: Figure-Experimental response of the divertor particle flux to internal transport barrier dynamics in EAST high-beta(N) discharges

description: Fig.1 shows the layout of the main diagnostics used in this work, including the divertor triple probe, AXUV ,etcFig.2 shows the temperal evolution of the plasma parameters in EAST high -betaN discharges with ITB in different configurations. The data are from measurement given by different diagnostics.Fig.4 (a) shows the density profiles at different time slices and (b) shows the time evolution of the density profile before and after the formation of ITB. They are meausred by TS, Refl. and POINT system in EASTFig.7 shows the response of divertor plasma to the ITB dynamics
description: Fig.1 shows the layout of the main diagnostics used in this work, including the divertor triple probe, AXUV ,etcFig.2 shows the temperal evolution of the plasma parameters in EAST high -betaN discharges with ITB in different configurations. The data are from measurement given by different diagnostics.Fig.4 (a) shows the density profiles at different time slices and (b) shows the time evolution of the density profile before and after the formation of ITB. They are meausred by TS, Refl. and POINT system in EASTFig.7 shows the response of divertor plasma to the ITB dynamics
DOI: 10.57760/sciencedb.03672
title: Laser induced ablation spectroscopy for in situ characterization of the ﬁrst wall on EAST tokamak
title: Laser induced ablation spectroscopy for in situ characterization of the ﬁrst wall on EAST tokamak

description: Plasma-wall interaction (PWI) is a crucial issue for high-performance operation and ﬁrst wall lifetime of future fusion reactors. An in situ measurement and the control of fuel retention in the vacuum-vessel will be an important aspect for the safe operation of nuclear fusion devices. Laser-Induced Ablation Spectroscopy (LIAS) is an attractive option with promising capabilities for in situ characterization of fuel retention and co-deposition during plasma discharges. In this work, an in situ LIAS wall diagnostic system is developed for real-time during discharge diagnosis of the ﬁrst wall on the EAST superconducting tokamak. A dedicated timing system, which oﬀers the function of multiple temporal settings with high time resolution for LIAS measurement during longpulse discharges, is successfully commissioned. The experimental setup of the LIAS system for the characterization of the ﬁrst wall on EAST is presented in detail. First LIAS results obtained in EAST during high power discharges are presented. The results indicate that in situ measurements of deposition, co-deposition and dynamic retention are possible.
description: Plasma-wall interaction (PWI) is a crucial issue for high-performance operation and ﬁrst wall lifetime of future fusion reactors. An in situ measurement and the control of fuel retention in the vacuum-vessel will be an important aspect for the safe operation of nuclear fusion devices. Laser-Induced Ablation Spectroscopy (LIAS) is an attractive option with promising capabilities for in situ characterization of fuel retention and co-deposition during plasma discharges. In this work, an in situ LIAS wall diagnostic system is developed for real-time during discharge diagnosis of the ﬁrst wall on the EAST superconducting tokamak. A dedicated timing system, which oﬀers the function of multiple temporal settings with high time resolution for LIAS measurement during longpulse discharges, is successfully commissioned. The experimental setup of the LIAS system for the characterization of the ﬁrst wall on EAST is presented in detail. First LIAS results obtained in EAST during high power discharges are presented. The results indicate that in situ measurements of deposition, co-deposition and dynamic retention are possible.
DOI: 10.57760/sciencedb.03674
title: picture of the AC loss
title: 交流损耗的图片

description: Relevant Results of AC Loss of Bi2223 High Temperature Superconducting Composite Conductor 
description: Relevant Results of AC Loss of Bi2223 High Temperature Superconducting Composite Conductor
DOI: 10.57760/sciencedb.03699
title: Figure-Analysis of dynamics and spatial structure on the filament during type I ELMy H-mode using VUVI system on EAST
title: Figure-Analysis of dynamics and spatial structure on the filament during type I ELMy H-mode using VUVI system on EAST

description: Fig.1 shows the view schematic layout of the VUVI system and the raw image with a size of 512x320pixels. It is a top view of a 3D plot by solidworks and the raw image was captured by the VUVI system.Fig.2 shows an example of SVD analysis result of the VUV imaging data. Fig.3 shows the result of the dynamics of filament width in one ELM cycle. The filament width are obtained by analyzing the reconstructed images by selecting the key compoents of the SVD analysis.Fig4. shows the dynamics of the poloidal velocity during an ELM crash. It is derived by calculating the relative changes on the position of the filament in two images in series. Fig.5 shows the two dimensional filament structures at different time slices, which are reconstructed using the key components of the SVD analysis of the imaging data.
description: Fig.1 shows the view schematic layout of the VUVI system and the raw image with a size of 512x320pixels. It is a top view of a 3D plot by solidworks and the raw image was captured by the VUVI system.Fig.2 shows an example of SVD analysis result of the VUV imaging data. Fig.3 shows the result of the dynamics of filament width in one ELM cycle. The filament width are obtained by analyzing the reconstructed images by selecting the key compoents of the SVD analysis.Fig4. shows the dynamics of the poloidal velocity during an ELM crash. It is derived by calculating the relative changes on the position of the filament in two images in series. Fig.5 shows the two dimensional filament structures at different time slices, which are reconstructed using the key components of the SVD analysis of the imaging data.
DOI: 10.57760/sciencedb.03677
title: Analysis data: A Rapid Nondestructive Inspection Method Applied to EAST Lower Divertor by Infrared Thermography
title: Analysis data: A Rapid Nondestructive Inspection Method Applied to EAST Lower Divertor by Infrared Thermography

description: The folder is the analysis data extracted from the raw data of infrared camera, including the temperature evolution of every tile and position illustration.
description: The folder is the analysis data extracted from the raw data of infrared camera, including the temperature evolution of every tile and position illustration.
DOI: 10.57760/sciencedb.03681
title: emotion cause event extraction dataset
title: 情绪诱因事件抽取数据集

description: This dataset is the dataset of the paper "A fine-grained emotion recognition method based on OCC model and emotion cause event extraction".1. Content: data on the topic of "Beijing Winter Olympic Games" in Sina Weibo2. Annotation:Text expectation category labeling and emotion cause event labeling
description: This dataset is the dataset of the paper "A fine-grained emotion recognition method based on OCC model and emotion cause event extraction".1. Content: data on the topic of "Beijing Winter Olympic Games" in Sina Weibo2. Annotation:Text expectation category labeling and emotion cause event labeling
DOI: 10.57760/sciencedb.03680
title: Analyses of deuterium retention in tungsten and graphite first wall materials by laser-induced ablation spectroscopy on EAST
title: Analyses of deuterium retention in tungsten and graphite first wall materials by laser-induced ablation spectroscopy on EAST

description: Plasma-wall interactions at the first wall in fusion experimental devices are critical for the life time of plasmafacing components and tokamak operation. In-situ measurements of these plasma-wall interaction processes are required in long pulse devices in order to understand better the underlying mechanisms as well as monitoring of the tritium content of the first wall as an immediate safety application. In this work we present measurements of the deuterium retention in the first wall of EAST using laser-induced ablation spectroscopy. The diagnostic is applied during plasma operation and the dynamic retention for graphite and tungsten as plasma-facing materials are compared, showing more than three times higher short-term retention in graphite than in tungsten. Laserbased analysis is applied during a shift of the vertical positions of the plasma column in limited as well as in the start-up phase of discharges in diverted magnetic configuration. Plasma core densities of n e = (1.5–3.2) × 10 19 /m3 are chosen to vary the ion flux to the first wall and study saturation effects of deuterium on the surface first wall materials during tokamak plasma operation. A linear dependence of the retention from ion fluence is observed for graphite as PFC up to 3 × 10 18 D+ /cm2 , followed by a constant retention up to fluences of 3.5 × 1019 D+ /cm2 for nearby first wall temperatures of T PFC ≈ 350 K.
description: Plasma-wall interactions at the first wall in fusion experimental devices are critical for the life time of plasmafacing components and tokamak operation. In-situ measurements of these plasma-wall interaction processes are required in long pulse devices in order to understand better the underlying mechanisms as well as monitoring of the tritium content of the first wall as an immediate safety application. In this work we present measurements of the deuterium retention in the first wall of EAST using laser-induced ablation spectroscopy. The diagnostic is applied during plasma operation and the dynamic retention for graphite and tungsten as plasma-facing materials are compared, showing more than three times higher short-term retention in graphite than in tungsten. Laserbased analysis is applied during a shift of the vertical positions of the plasma column in limited as well as in the start-up phase of discharges in diverted magnetic configuration. Plasma core densities of n e = (1.5–3.2) × 10 19 /m3 are chosen to vary the ion flux to the first wall and study saturation effects of deuterium on the surface first wall materials during tokamak plasma operation. A linear dependence of the retention from ion fluence is observed for graphite as PFC up to 3 × 10 18 D+ /cm2 , followed by a constant retention up to fluences of 3.5 × 1019 D+ /cm2 for nearby first wall temperatures of T PFC ≈ 350 K.
DOI: 10.57760/sciencedb.03683
title: Comparison of active impurity control between lithium and boron powder real-time injection in EAST
title: EAST上锂粉和硼粉实时注入控制杂质实验研究

description: The data of comparison of active impurity control between lithium and boron powder real-time injection in EAST
description: The data of comparison of active impurity control between lithium and boron powder real-time injection in EAST
DOI: 10.57760/sciencedb.03687
title: Simulation studies of divertor power exhaust with neon seeding for CFETR with GW-level fusion power
title: Simulation studies of divertor power exhaust with neon seeding for CFETR with GW-level fusion power

description: A conventional single null divertor geometry has been proposed for Chinese fusion engineering testing reactor (CFETR) with fusion powerup to gigawatt level. Modeling using the SOLPS5.0 code package shows promising results for divertor power exhaust by seeding with neon(Ne) and deuterium (D2 ). Partial detachment for both inner and outer divertor targets can be achieved with a peak heat load lower than3MW/m 2 . The effective ion charge number, Z_eff , at the core boundary is below three, which can be further reduced by increasing theupstream D2 puffing rate. A higher D2 puffing rate helps to increase electron density (ne ) in scrape-off layer (SOL) and the impurity screen-ing ability. Based on the SOLPS modeling results, the lifetime of tungsten (W) divertor targets has been estimated by using the DIVIMPcode, which indicates that W sputtering is mainly contributed by Ne ions at a far SOL region due to high electron and ion temperature(Te and Ti ) there. Upstream D2 puffing can reduce the W erosion rate and W impurity concentration inside the separatrix due to decreasingTe and Ti at the far SOL region. The modeling results show a viable operation regime for the CFETR divertor.
description: A conventional single null divertor geometry has been proposed for Chinese fusion engineering testing reactor (CFETR) with fusion powerup to gigawatt level. Modeling using the SOLPS5.0 code package shows promising results for divertor power exhaust by seeding with neon(Ne) and deuterium (D2 ). Partial detachment for both inner and outer divertor targets can be achieved with a peak heat load lower than3MW/m 2 . The effective ion charge number, Z_eff , at the core boundary is below three, which can be further reduced by increasing theupstream D2 puffing rate. A higher D2 puffing rate helps to increase electron density (ne ) in scrape-off layer (SOL) and the impurity screen-ing ability. Based on the SOLPS modeling results, the lifetime of tungsten (W) divertor targets has been estimated by using the DIVIMPcode, which indicates that W sputtering is mainly contributed by Ne ions at a far SOL region due to high electron and ion temperature(Te and Ti ) there. Upstream D2 puffing can reduce the W erosion rate and W impurity concentration inside the separatrix due to decreasingTe and Ti at the far SOL region. The modeling results show a viable operation regime for the CFETR divertor.
DOI: 10.57760/sciencedb.03696
title: Data of TALIF measurements of hydrogen and deuterium surface loss probabilities on quartz in low pressure high density plasmas
title: Data of TALIF measurements of hydrogen and deuterium surface loss probabilities on quartz in low pressure high density plasmas

description: This article deals with surface loss on quartz of atomic hydrogen (H) and its isotope deuterium(D) in a low-pressure (10 Pa) pulsed inductively coupled plasma. The atomic temporal decayin the post discharge is measured by two-photon absorption laser-induced fluorescence(TALIF). From the loss rate, the atomic surface loss probability is determined. In purehydrogen or pure deuterium gas, no isotopic effect on surface kinetics has been observed andthe surface loss probabilities of H and D were found to be almost identical and equal to∼1.8%. However, despite the lack of difference in surface loss probability, a net isotopic effecton surface loss rate due to the mass difference between the isotopes is measured. Hydrogenatoms diffuse faster and have higher flux to the plasma chamber walls than deuterium atoms.Hydrogen atoms are therefore lost at higher rate than deuterium atoms. Based on the observedisotopic difference and on the comparison between H and D TALIF signals, the isotopiceffects on H and D atom production are discussed.
description: This article deals with surface loss on quartz of atomic hydrogen (H) and its isotope deuterium(D) in a low-pressure (10 Pa) pulsed inductively coupled plasma. The atomic temporal decayin the post discharge is measured by two-photon absorption laser-induced fluorescence(TALIF). From the loss rate, the atomic surface loss probability is determined. In purehydrogen or pure deuterium gas, no isotopic effect on surface kinetics has been observed andthe surface loss probabilities of H and D were found to be almost identical and equal to∼1.8%. However, despite the lack of difference in surface loss probability, a net isotopic effecton surface loss rate due to the mass difference between the isotopes is measured. Hydrogenatoms diffuse faster and have higher flux to the plasma chamber walls than deuterium atoms.Hydrogen atoms are therefore lost at higher rate than deuterium atoms. Based on the observedisotopic difference and on the comparison between H and D TALIF signals, the isotopiceffects on H and D atom production are discussed.
DOI: 10.57760/sciencedb.03688
title: Magnetic field distribution of CFETR TF magnet in different states
title: CFETR在不同状态下TF磁体的磁场分布

description: The magnetic field distribution of CFETR TF magnet under three normal modes like ITER, super X and snowflake and two fault modes of short circuit and quench 
description: The magnetic field distribution of CFETR TF magnet under three normal modes like ITER, super X and snowflake and two fault modes of short circuit and quench
DOI: 10.57760/sciencedb.03693
title: RawData：Effect of pedestal fluctuation on ELM frequency in the EAST tokamak
title: RawData：Effect of pedestal fluctuation on ELM frequency in the EAST tokamak

description: Dependence of ELM frequency (fELM) and energy loss (WELM) on heating power through the separatrix (Psep)
description: Dependence of ELM frequency (fELM) and energy loss (WELM) on heating power through the separatrix (Psep)