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Cross-field plasma transport in divertor and divertor plasma detachment

机译：转向器和隅钢体等离子体脱离中的跨场等离子传输

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I. Introduction Detached (or partially detached) divertor regime is currently considered mandatory for ITER and future tokamak-reactors [1]. Its realization relies on intensive power loss by the impurity radiation from divertor volume [2]. In tokamaks with carbon PFCs the main radiation loss is usually due to carbon, sputtering of which is virtually uncontrollable. In tokamaks with metal walls (e.g. JET) radiation loss with impurity generated by sputtering of the PFCs is relatively small. In order to reach divertor detachment, one has to inject impurities (e.g. nitrogen or neon). As a result, the amount of impurity becomes a controllable parameter. However, impurity localization and, therefore, the radiation loss in divertor volume is determined by an interplay of drifts and classical parallel and anomalous cross-field transport. Simple models (see for example [3]) predict that the cross-field heat transport can significant enhance the impurity radiation loss in relatively cold divertor plasma, where parallel heat conduction is limited.
机译：I.介绍分离（或部分独立）的转型制度目前被认为是ITER和未来Tokamak反应堆的强制性[1]。它的实现依赖于杂质辐射的强化功率损失[2]。在碳PFC的托卡马克斯，主要辐射损失通常是由于碳，溅射几乎无法控制。在与金属壁（例如喷射）通过溅射产生的杂质的金属壁（例如喷射）的辐射损失相对较小。为了达到倾斜器脱离，必须进入杂质（例如氮气或氖）。结果，杂质的量成为可控参数。然而，杂质定位和因此，转移体积中的辐射损失由漂移和经典平行和异常的跨场传输的相互作用来确定。简单的模型（参见例如[3]）预测跨场热传输可以显着增强相对冷的偏离器等离子体中的杂质辐射损失，其中平行的热传导是有限的。

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