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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >PLASMA-SURFACE INTERACTIONS IN THE ALCATOR C-MOD TOKAMAK
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PLASMA-SURFACE INTERACTIONS IN THE ALCATOR C-MOD TOKAMAK

机译:铝电解器C-MOD托卡马克中的等离子体-表面相互作用

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摘要

Alcator C-Mod is a high-field tokamak with which experiments were initiated in April 1993. The divertor and the first-wall have plasma-facing surfaces of molybdenum. The divertor has a configuration which is closed in comparison to other, currently operating tokamaks, The combination of divertor geometry and high field (density) make Alcator C-Mod an ideal experiment to investigate dissipative (radiative/CX) divertor scenarios. Single-null divertor operation has become the standard mode of operation. Relatively clean plasmas (Z(eff)less than or equal to 1.3) are obtained with short periods of baking and electron cyclotron discharge cleaning only. Impurity source rates and screening have been investigated with an extensive set of wavelength-filtered diode arrays and spectrographs. Carbon and oxygen and molybdenum dominate the impurity levels. The molybdenum source from the divertor proper is negligible. [References: 10]
机译:Alcator C-Mod是一种高场托卡马克,于1993年4月开始进行实验。分流器和第一壁具有面向等离子体的钼表面。与其他目前正在运行的托卡马克相比,分流器的配置是封闭的。分流器几何形状和高场(密度)的结合使Alcator C-Mod成为研究耗散(辐射/ CX)分流器场景的理想实验。单零偏滤器操作已成为标准操作模式。仅通过短时间的烘烤和电子回旋加速器放电清洁就可以获得相对清洁的等离子体(Z(eff)小于或等于1.3)。杂质源的速率和屏蔽已通过大量的波长滤波二极管阵列和光谱仪进行了研究。碳,氧和钼占主导地位。来自偏滤器的钼源可以忽略不计。 [参考:10]

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