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Implications of convective scrape-off layer transport for fusion reactors with solid and liquid walls

机译:对流刮除层传输对具有固体和液体壁的聚变反应堆的影响

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Recent experimental observations in tokamaks indicate enhanced convection of plasma blobs toward the main chamber wall. Potential implications of these observations for reactors are examined here. Two-dimensional plasma edge calculations are performed with UEDGE, including convective transport consistent with present experiments. This is coupled to a kinetic neutral calculation using the code NUT, to compute the hot neutral flux to the wall. The inclusion of convection increases sputtering of the wall by roughly an order of magnitude. For tungsten walls, erosion (neglecting re-deposition) is estimated to be ~.6 mm year~(-1). The enhanced source of impurities for high Z walls requires an enhanced plasma screening factor to allow ignition. Low Z liquid materials enable acceptable plasma contamination with much lower screening factors. Rough estimates of dust generation from erosion rates with convection imply significant safety issues. Plasma transport via blobs can also strongly modify models of impurity screening and redeposition, and represents a potential feasibility issue in need of further research.
机译:最近在托卡马克中的实验观察表明,等离子体斑点向主室壁的对流增强。这些观察对反应堆的潜在影响在此进行了检查。用UEDGE进行二维等离子体边缘计算,包括与当前实验一致的对流传输。这与使用代码NUT的动力学中性计算相结合,以计算到壁的热中性通量。对流的包含使壁的溅射增加了大约一个数量级。对于钨壁,腐蚀(忽略再沉积)估计为〜.6 mm年(-1)。用于高Z壁的杂质源的增加要求等离子体屏蔽因子的增加以允许点火。低Z液体材料可实现可接受的等离子体污染,且屏蔽系数低得多。根据对流的侵蚀速率粗略估计产生的粉尘意味着重大的安全问题。经由斑点的等离子体运输还可以强烈地改变杂质筛选和再沉积的模型,并且代表了需要进一步研究的潜在可行性问题。

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