DIVIMP modeling of tungsten impurity transport in ITER
DIVIMP modeling of tungsten impurity transport in ITER
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DOI：
10.1016/j.jnucmat.2007.01.045
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发表时间：
2007-06
影响因子：
3.1
通讯作者：
Klaus Schmid;K. Krieger;A. Kukushkin;A. Loarte
中科院分区：
文献类型：
--
作者：
Klaus Schmid;K. Krieger;A. Kukushkin;A. Loarte
本文采用蒙特卡罗杂质输运程序DIVIMP模拟研究了ITER中不同第一壁W覆盖率和等离子体结构下的W侵蚀和等离子体积累。基于B2/EIRENE背景等离子体溶液的离子通量，通过考虑D和杂质离子（C，Ar和He）来计算W的侵蚀。基于这些W侵蚀通量的W等离子体浓度计算。标准的稳态偏滤器等离子体几何形状和限制器的几何形状模仿ITER斜升进行计算。计算表明，在稳态偏滤器操作的W侵蚀和等离子体浓度是低的，即使当W的第一壁覆盖率增加到一个完整的W ITER。在限制器几何结构中，由于靠近W限制器的电子温度很高，即使对于纯D等离子体也观察到强烈的W侵蚀。当种子杂质被考虑在内，不可容忍的W等离子体浓度的几个百分点，观察到在限制器等离子体配置。
This paper presents a modeling study of the W erosion and plasma accumulation in ITER for different levels of first wall W coverage and plasma configurations using the Monte Carlo impurity transport code DIVIMP. Based on the ion fluxes from the background plasma solutions from B2/EIRENE the W erosion is calculated by taking into account both D and impurity ions (C, Ar and He). Based on these W erosion fluxes the W plasma concentrations are calculated. The calculations are performed for standard steady state divertor plasma geometry and for limiter geometry mimicking the ITER ramp up. The calculations show that in steady state divertor operation the W erosion and plasma concentrations are low even when the W first wall coverage is increased to a full W ITER. In limiter geometry due to the high electron temperatures close to the W limiter, strong W erosion is observed even for pure D plasmas. When seeded impurities are taken into account, intolerable W plasma concentrations of several percent are observed in the limiter plasma configuration.