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基于EAST装置量热系统的第一壁热负荷实验研究 认领
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作者 庄清 明廷凤 +10 位作者 余耀伟 煜锴 周凡 龙飞飞 杨雷 李沂隆 王嵎民 海庆 李国强 高翔 《核聚变与等离子体物理》 CAS CSCD 北大核心 2020年第3期222-226,共5页
通过测量EAST装置水冷系统的出入口冷却水的温差和流量,搭建了第一壁热负荷测量系统,实现了第一壁热负荷的分布测量。实验结果表明,在上单零偏滤器位形放电实验中,该系统测量的热负荷约占总注入能量的80%,其中,接近50%的热负荷沉积在上... 通过测量EAST装置水冷系统的出入口冷却水的温差和流量,搭建了第一壁热负荷测量系统,实现了第一壁热负荷的分布测量。实验结果表明,在上单零偏滤器位形放电实验中,该系统测量的热负荷约占总注入能量的80%,其中,接近50%的热负荷沉积在上偏滤器区域。高的加热功率会使得第一壁热负荷更快上升。通过冷却水降温曲线拟合计算得出EAST装置上钨偏滤器水冷系统的热衰减时间约为下石墨偏滤器水冷系统的十分之一。 展开更多
关键词 热负荷 热负荷测量系统 长脉冲 水冷系统 EAST
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Observation of filament-like structures in ELMy H-mode plasma with a VUV imaging system developed on the EAST tokamak 认领
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作者 周凡 明廷凤 +6 位作者 王嵎民 龙飞飞 庄清 李国强 高翔 EAST team 《等离子体科学与技术:英文版》 SCIE EI CAS CSCD 2019年第9期19-24,共6页
On the EAST tokamak,filament-like structures have been observed in ELMy H-mode discharges with a high-speed vacuum ultraviolet (VUV) imaging system.The topos,chronos and their weight can be obtained simultaneously by ... On the EAST tokamak,filament-like structures have been observed in ELMy H-mode discharges with a high-speed vacuum ultraviolet (VUV) imaging system.The topos,chronos and their weight can be obtained simultaneously by performing the so-called singular value decomposition (SVD) analysis of raw VUV imaging data.The fluctuation amplitude is observed to be suppressed and enhanced gradually in the edge localized mode (ELM) crash and pedestal recovery phase in the chronos,respectively,while filament-like structures can only be found in the pedestal recovery phase on the topos.The mode structure,i.e.m/n =36/9 (m and n are the poloidal and toroidal mode number,respectively) with ρ0 =0.95,w0 =0.07 (ρ0 and w0 denote the mode location and mode width,respectively) is derived by a comparison of the synthetic images and the experimental imaging data. 展开更多
关键词 VUV ELMS SVD filament-like structure mode number
Modeling of divertor power footprint widths on EAST by SOLPS5.0/B2.5-Eirene 认领
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作者 邓国忠 晓菊 +6 位作者 王亮 许吉禅 冯威 建斌 高翔 《等离子体科学与技术:英文版》 SCIE EI CAS CSCD 2017年第4期28-33,共6页
The edge plasma code package SOLPS5.0 is employed to simulate the divertor power footprint widths of the experimental advanced superconducting tokamak(EAST)L-mode and ELM-free H-mode plasmas.The divertor power footpri... The edge plasma code package SOLPS5.0 is employed to simulate the divertor power footprint widths of the experimental advanced superconducting tokamak(EAST)L-mode and ELM-free H-mode plasmas.The divertor power footprint widths,which consist of the scrape-off layer(SOL)widthλ_q and heat spreading 5,are important physical parameters for edge plasmas.In this work,a plasma current scan is implemented in the simulation to obtain the dependence of the divertor power footprint width on the plasma current I_p.Strong inverse scaling of the SOL width with I_p has been achieved for both L-mode and H-mode plasmas in the forms ofλq,L-mode=4.98×I_p~(-0.68)andλq,H-mode=1.86×I_p~(-1.08).Similar trends have also been demonstrated in the study of heat spreading with SL-mode=1.95×I_p~(-0.542)and SH-mode=0.756×I_p~(-0.872).In addition,studies on divertor peak heat load and the magnetic flux expansion factor show that both of them are proportional to plasma current.The simulation work here can act as a way to explore the power footprint widths of future tokamak fusion devices such as ITER and the China Fusion Engineering Test Reactor(CFETR). 展开更多
关键词 反应堆功率 偏滤器 宽度 等离子体边缘 等离子体电流 托卡马克实验装置 托卡马克聚变装置 建模
Achieving temporary divertor plasma detachment with MARFE events by pellet injection in the EAST superconducting tokamak 认领
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作者 邓国忠 王亮 +14 位作者 晓菊 段艳敏 胡建生 李长征 张凌 汪惠乾 陈良 许吉禅 冯威 建斌 徐国盛 郭后扬 高翔 《等离子体科学与技术:英文版》 SCIE EI CAS CSCD 2017年第1期29-35,共7页
A new pellet injection system has been equipped on the experimental advanced superconducting tokamak(EAST) in the 2012 campaign,with a pellet size of Ф 2 mm?×?2 mm,a frequency of1 Hz–10 Hz and velocity of 150 m... A new pellet injection system has been equipped on the experimental advanced superconducting tokamak(EAST) in the 2012 campaign,with a pellet size of Ф 2 mm?×?2 mm,a frequency of1 Hz–10 Hz and velocity of 150 m s~(-1)–300 m s~(-1).The deuterium pellet is well-known for plasma fuelling as well as for? triggering the edge localized mode(ELM).In the 2012 campaign,pellet injection experiments were successfully carried out on EAST.Temporary plasma detachment achieved by deuterium pellets has been observed in a double null(DN) divertor configuration,with multi-pellet injections at a repetition frequency of 2 Hz.The partial detachment of the outer divertors and complete detachment of the inner divertors was achieved after 35 ms of each pellet injection,which have a duration of 30–60 ms with the maximum degree of detachment(DOD) reaching 3.5 and 37,respectively.Meanwhile,the multifaceted asymmetric radiation from the edge(MARFE) phenomena was also observed at the high field side(HFS) near both the lower and upper X-points with radiation loss suddenly increased to about 15%–70%,which may be the main cause of divertor plasma detachment.The temporary detachment induced by pellet injection may act as a new way to study divertor detachment behaviors. 展开更多
关键词 弹丸注入系统 等离子体加料 超导托卡马克 MARFE EAST 偏滤器 托卡马克实验装置 颗粒大小
全超导托卡马克装置(EAST)充气成像系统光学设计 认领
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作者 陈素娟 陈结祥 《应用光学》 CAS CSCD 北大核心 2016年第2期187-191,共5页
为了观测全超导托卡马克装置(EAST)中充气成像系统(gas puff imaging,GPI)的谱线强度,提出一套GPI光学观察系统。以匹兹伐型物镜为初始结构进行优化,使系统像差控制在1/4λ内,在观察波长656.2nm/587.6nm下,设计系统光学传递函数在16... 为了观测全超导托卡马克装置(EAST)中充气成像系统(gas puff imaging,GPI)的谱线强度,提出一套GPI光学观察系统。以匹兹伐型物镜为初始结构进行优化,使系统像差控制在1/4λ内,在观察波长656.2nm/587.6nm下,设计系统光学传递函数在16lp/mm下达到了0.76。对温度参数在20°-250°范围内作多重结构分析,选取的透镜材料热膨胀系数非常相近,光学频率在16lp/mm时,子午方向的光学传递函数几乎无变化,而弧氏方向的光学传递函数由0.82变化到了0.69。根据光学观察窗口所在物理环境,对其进行静力学、热力学仿真研究,可以看到石英窗口的形变量达到了1/5λ,将该形变代入光学设计中进行容差分析,系统的MTF≥0.5。通过快速相机捕捉到的系统成像光谱画面图显示,该系统能清晰地观察物面的谱线强度分布以及变化。 展开更多
关键词 光学设计 充气成像 辐射诊断 静力学仿真
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Long Pulse H-Mode Scenarios Sustained by RF Heating on EAST 认领
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作者 高翔 李国强 +14 位作者 张涛 杨曜 龚先祖 子奚 任启龙 海庆 曾龙 余耀伟 晓菊 张寿彪 蔡辉山 吴雪梅 李建刚 the EAST team 《等离子体科学与技术:英文版》 SCIE EI CAS CSCD 2015年第6期448-453,共6页
东方在过去的实验表明了它长脉搏操作使用 RF 加热的能力(LHCD 和 ICRF ) 。认识到长脉搏 H 模式实验的一个关键问题为稳定的州的操作是支撑血浆当前的。基于运输代码 ONETWO 和它的联合 RF 代码 GENRAY 的计算,二种情形被建议了完成 1... 东方在过去的实验表明了它长脉搏操作使用 RF 加热的能力(LHCD 和 ICRF ) 。认识到长脉搏 H 模式实验的一个关键问题为稳定的州的操作是支撑血浆当前的。基于运输代码 ONETWO 和它的联合 RF 代码 GENRAY 的计算,二种情形被建议了完成 10 s H 模式血浆与我 <SUB > p </SUB>=400 kA, < n <SUB > e </SUB>>=4.5 牧敥敭瑮眠獡映畯摮 展开更多
关键词 射频加热 EAST 长脉冲 H模式等离子体 低杂波电流驱动 等离子体电流 ICRF LHCD
Observation of Pedestal Plasma Turbulence on EAST Tokamak 认领 被引量:1
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作者 高翔 张涛 +8 位作者 韩翔 张寿彪 王嵎民 子奚 杨曜 史楠 凌必利 李建刚 《等离子体科学与技术:英文版》 SCIE EI CAS CSCD 2013年第8期732-737,共6页
关键词 EAST装置 托卡马克实验 等离子体湍流 立柱 ELM 高频率 微波反射 时空演化
Radiative Divertor Plasma Behavior in L-and H-Mode Discharges with Argon Injection in EAST 认领
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作者 王东升 郭后扬 +9 位作者 尚毅梓 甘开福 汪惠乾 陈颖杰 王亮 高伟 向玲燕 吴振伟 罗广南 《等离子体科学与技术:英文版》 SCIE EI CAS CSCD 2013年第7期614-618,共5页
关键词 辐射偏滤器 H模式放电 等离子体 氩气 注射液 行为 杂质含量 实验活动
Reciprocating Probe Measurements of L-H Transition in LHCD H-Mode on EAST 认领 被引量:1
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作者 徐国盛 +6 位作者 汪惠乾 蒋敏 王亮 张炜 颜宁 丁斯晔 《等离子体科学和技术:英文版》 SCIE EI CAS CSCD 2013年第7期619-622,共4页
As the power available in the initial phase of the ITER operation will be limited, accessing the high confinement mode (H-mode) with low heating power will be a critical issue. In the recent experiment on EAST, the H-... As the power available in the initial phase of the ITER operation will be limited, accessing the high confinement mode (H-mode) with low heating power will be a critical issue. In the recent experiment on EAST, the H-mode was obtained for the first time with lower hybrid current drive (LHCD) wave only. Reciprocating Langmuir probe measurements at the outer midplane showed that the electron density n e and electron temperature T e in the scrape-off layer (SOL) were significantly reduced in the ELM-free phase, resulting in the increase of lower-hybrid wave (LHW) reflection. It was found that the power loss P loss was comparable during the L-H transition, by comparing the adjacent L-mode and H-mode discharge. The Dα emission, T e and n e decreased rapidly in the time scale of about 1 ms, and the radial electric field E r turned positive in this process near the last closed flux surface. Multiple L-H-L transitions were observed during a single shot when the applied LHW power was marginal to the threshold. The floating potential (Vf ) had negative spikes corresponding with the Dα signal, and E r oscillation evolved into several intermittent negative spikes just before the L-H transition. In some shots, dithering was observed just before the L-H transition. 展开更多
关键词 低杂波电流驱动 H模式放电 LHCD 朗缪尔探针 EAST 国际热核实验堆 测量 加热功率
东方超环托卡马克高约束模式边界等离子体输运数值模拟研究 认领 被引量:2
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作者 杜海龙 桑超峰 +6 位作者 王亮 孙继忠 汪惠乾 张凌 郭后扬 王德真 《物理学报》 SCIE EI CAS CSCD 北大核心 2013年第24期229-238,共10页
利用SOLPS5.0模拟研究东方超环托卡马克(EAST)高约束模式时的刮削层等离子体.在高约束模式放电实验参数(第36291炮)的限制下,通过调整上游区径向反常输运系数来实现高约束模式模拟,在上游电子密度和温度与实验符合的条件下能够很好... 利用SOLPS5.0模拟研究东方超环托卡马克(EAST)高约束模式时的刮削层等离子体.在高约束模式放电实验参数(第36291炮)的限制下,通过调整上游区径向反常输运系数来实现高约束模式模拟,在上游电子密度和温度与实验符合的条件下能够很好地进行下游区模拟.在实现高约束模拟的基础上又分别研究了漂移项对偏滤器靶板能流不对称性的影响和上游能流衰减宽度对靶板能流密度峰值的影响.通过模拟发现,漂移是导致EAST放电内外靶板不对称性的主要原因,增大上游能流衰减宽度可以明显降低入射到靶板的峰值热流,并且偏滤器区辐射以及与中性粒子的相互作用减小了能流的衰减宽度对达到靶板能流的影响. 展开更多
关键词 托卡马克 高约束模式 SOLPS5 0 漂移
A Dip Structure in the Intrinsic Toroidal Rotation Near the Edge of the Ohmic Plasmas in EAST 认领
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作者 徐国盛 V. NAULIN +20 位作者 万宝年 郭后扬 张炜 常加峰 颜宁 丁斯晔 张凌 王亮 蒋敏 汪惠乾 J. Juul RASMUSSEN A. H. NIELSEN 肖持进 高翔 胡立群 朱思铮 吴振伟 钱金平 龚先祖 《等离子体科学和技术:英文版》 SCIE EI CAS CSCD 2011年第4期397-404,共8页
<正> Ion’s toroidal velocity,v_t,in both the outermost 4 cm of the confined region and thescrap-off layer of Ohmic L-mode plasmas in EAST was measured using Mach probes.At about1 cm inside the separatrix a loca... <正> Ion’s toroidal velocity,v_t,in both the outermost 4 cm of the confined region and thescrap-off layer of Ohmic L-mode plasmas in EAST was measured using Mach probes.At about1 cm inside the separatrix a local minimum in v_t was observed,from which a cocurrent rotationincreased both inwards and outwards.The radial width of the v_t dip was 1 cm to 2 cm,andboth the density and electron temperature profiles exhibited steep gradients at this dip position.It was observed in both divertor and limiter configurations.To find out its origin,the toroidaltorques induced by neutral friction,neoclassical viscosity,collisional perpendicular shear viscosity,ion orbit loss and turbulent Reynolds stress were estimated using the measured parameters.Ourresults indicate that in this particular parameter regime the neutral friction was the dominantdamping force.The calculated cocurrent toroidal torque by the neoclassical viscosity dominatesover those from the collisional perpendicular shear viscosity,ion orbit loss and turbulent Reynoldsstress.These results are potentially important for the understanding of boundary conditions forthe intrinsic toroidal momentum in tokamak plasmas. 展开更多
关键词 等离子体边缘 环形 IP结构 旋转 欧姆 托卡马克等离子体 新古典主义 剪切粘度
Observation of Blobs and Holes in the Boundary Plasma of EAST Tokamak 认领
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作者 颜宁 徐国盛 +13 位作者 张炜 常加峰 王亮 汪惠乾 蒋敏 熊豪 丁斯晔 万宝年 高翔 V. NAULIN A. H. NIELSEN J. Juul RASMUSSEN 《等离子体科学和技术:英文版》 SCIE EI CAS CSCD 2011年第4期410-414,共5页
<正> Intermittent convective transport at the edge and in the scrape-off layer(SOL)ofEAST was investigated by using fast reciprocating Langmuir probe.Holes,as part of plasmastrTictures,were detected for the firs... <正> Intermittent convective transport at the edge and in the scrape-off layer(SOL)ofEAST was investigated by using fast reciprocating Langmuir probe.Holes,as part of plasmastrTictures,were detected for the first time inside the shear layer.The amplitude probabilitydistribution function of the turbulence is strongly skewed,with positive skewed events("blobs")prevailing in the SOL region and negative skewed events("holes")dominant inside the shearlayer.The statistical properties coincide with previous observations from JET.The generationmechanism of blobs and holes is also discussed.In addition burst structure and dynamics characterof them are also presented. 展开更多
关键词 等离子体 BLOB 托卡马克 边界 概率分布函数 朗缪尔探针 对流运输 统计特性
Study of Scrape-Off-Layer Width in Ohmic and Lower Hybrid Wave Heated Double-Null Divertor Plasma in EAST 认领
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作者 王亮 徐国盛 +16 位作者 常加峰 张炜 颜宁 丁斯晔 明廷凤 汪惠乾 蒋敏 熊豪 万宝年 高翔 郭后扬 胡立群 吴振伟 朱思铮 罗广南 《等离子体科学和技术:英文版》 SCIE EI CAS CSCD 2011年第4期435-439,共5页
<正> Edge profiles in Ohmic and lower hybrid(LH)wave heated discharges in EASTare presented.A comparison of the measured profiles is made with those from the theoreticalprediction for the scrape-off-layer(SOL)wi... <正> Edge profiles in Ohmic and lower hybrid(LH)wave heated discharges in EASTare presented.A comparison of the measured profiles is made with those from the theoreticalprediction for the scrape-off-layer(SOL)width.The edge plasma parameters are diagnosed bya triple probe divertor diagnostic system and fast reciprocating probes at the outer mid-plane.The experimental results show that the SOL width of double-null(DN)divertor plasmas in EASTappears to exhibit a negative dependence on the power crossing the separatrix,which is consistentwith the collisional SOL scalings of JET and Alcator C-Mod.This will provide useful informationfor extrapolation to the ITER SOL width scaling for power deposition. 展开更多
关键词 等离子体参数 偏滤器 波加热 宽度 电阻 国际热核实验堆 混杂 关闭
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