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Influence of the X-point location on edge plasma transport in the J-TEXT tokamak with a high-field-side single-null divertor
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作者 Hao WANG Yunfeng LIANG +19 位作者 Shuai XU Zhonghe JIANG Yuhe FENG A KNIEpS p drews Jie YANG Xin XU Ting LONG Shaodong JIAO Xiaolong ZHANG Zhigang HAO Qinglong YANG Zhipeng CHEN Zhongyong CHEN Nengchao WANG Zhoujun YANG Xiaoqing ZHANG Yonghua DING Yuan pAN the J-TEXT Team 《Plasma Science and Technology》 SCIE EI CAS CSCD 2021年第12期42-54,共13页
High-density experiments in the high-field-side mid-plane single-null divertor configuration have been performed for the first time on J-TEXT.The experiments show an increase in the highest central channel line-averag... High-density experiments in the high-field-side mid-plane single-null divertor configuration have been performed for the first time on J-TEXT.The experiments show an increase in the highest central channel line-averaged density from 2.73×10^(19)m^(-3) to 6.49×10^(19)m^(-3),while the X-point moves away from the target by increasing the divertor coil current.The corresponding Greenwald fraction rises from 0.50 to 0.79.For the impurity transport,the density normalized radiation intensity(absolute extreme ultraviolet and soft x-ray)of the central channel density decreased significantly(>50%)with an increase in the plasma density.To better understand the underlying physics mechanisms,the 3 D edge Monte Carlo code coupled with EIRENE(EMC3-EIRENE)has been implemented for the first time on J-TEXT.The simulation results show good agreement with the experimental findings.As the X-point moves away from the target,the divertor power decay length drops and the scrape-off layer impurity screening effect is enhanced. 展开更多
关键词 edge plasma transport divertor configuration EMC3-EIRENE
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Numerical estimate of multi-species ion sound speed of Langmuir probe interpretations in the edge plasmas of Wendelstein 7-X
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作者 J COSFELD p drews +5 位作者 B BLACKWELL M JAKUBOWSKI H NIEMANN D ZHANG Y FENG the Wendelstein-X Team 《Plasma Science and Technology》 SCIE EI CAS CSCD 2020年第8期63-70,共8页
The recently modified EMC3-EIRENE code package has been widely applied as an edge-plasma analysis tool and resulted in successful validation against various measured trends seen in stellarator and tokamak plasma bound... The recently modified EMC3-EIRENE code package has been widely applied as an edge-plasma analysis tool and resulted in successful validation against various measured trends seen in stellarator and tokamak plasma boundaries.It has been shown that the code package applied for Wendelstein 7-X(W7-X)discharges in the interpretive mode can assess the impact of impurity effects on the electron density,measured by a set of Langmuir probes.In particular the spatial quantification of impurities and effects from the effective charge state Zeff and effective mass meff,which are non-trivial to record by diagnostics,were examined.The results showed that earlier assumptions of the effective charge-state distribution and effective mass for reported Langmuir probe measurements must be revised.Subsequently,reprocessing these measurements with code-interpreted spatial profiles of the effective charge state and effective mass led to an overall improved physical consistency. 展开更多
关键词 Wendelstein 7-X plasma-wall interaction numerical-diagnostics EMC3-EIRENE
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Magnetic configuration effects on the edge heat flux in the limiter plasma on W7-X measured using the infrared camera and the combined probe
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作者 p drews H NIEMANN +19 位作者 J COSFELD Y GAO J GEIGER O GRULKE M HENKEL D HOSCHEN K HOLLFELD C KILLER A KRAMER-FLECKEN Y LIANG S LIU D NICOLAI O NEUBAUER M RACK B SCHWEER G SATHEESWARAN L RUDISCHHAUSER N SANDRI N WANG the W7-X Team 《Plasma Science and Technology》 SCIE EI CAS CSCD 2018年第5期18-22,共5页
Controlling the heat and particle fluxes in the plasma edge and on the plasma facing components is important for the safe and effective operation of every magnetically confined fusion device.This was attempted on Wend... Controlling the heat and particle fluxes in the plasma edge and on the plasma facing components is important for the safe and effective operation of every magnetically confined fusion device.This was attempted on Wendelstein 7-X in the first operational campaign,with the modification of the magnetic configuration by use of the trim coils and tuning the field coil currents,commonly named iota scan.Ideally,the heat loads on the five limiters are equal.However,they differ between each limiter and are non-uniform,due to the(relatively small) error fields caused by the misalignment of components.It is therefore necessary to study the influence of the configuration changes on the transport of heat and particles in the plasma edge caused by the application of error fields and the change of the magnetic configuration.In this paper the upstream measurements conducted with the combined probe are compared to the downstream measurements with the DIAS infrared camera on the limiter. 展开更多
关键词 Wendelstein 7-X W7-X plasma edge heat flux LIMITER
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