Survey of tungsten gross erosion from main plasma facing components in WEST during a L-mode high fluence campaign

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
N. Fedorczak , C. Arnas , L. Cappelli , L. Colas , Y. Corre , M. Diez , A. Gallo , J. Gaspar , A. Grosjean , C. Guillemaut , J.P. Gunn , C. Johnson , C. Martin , E. Tsitrone , E.A. Unterberg , J. Bucalossi , WEST team
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Abstract

An initial high fluence campaign was performed in WEST, in 2023, on the newly installed actively cooled tungsten divertor composed of ITER-grade monoblocks. The campaign consisted in the repetition of a 60 s long Deuterium L-mode pulse in attached divertor conditions, cumulating over 10000s of plasma exposure. A maximum deuterium fluence of approximately 51026 m−2 was reached in the outer strike point region, representative of a few high performance ITER pulses. Gross tungsten erosion inferred from visible spectroscopy shows that the most eroded plasma facing component is the inner divertor target with rates ten times larger than on the outer divertor target. The outer midplane tungsten bumpers, located a few centimeters from the plasma, show gross erosion rates two times lower than at the outer divertor. We conclude that the outer midplane bumpers have a negligible contribution to the long range tungsten migration and deposition onto the lower divertor. The cumulated gross erosion rate on the inner divertor translates in an effective gross erosion thickness of about 20μm, while it is about 2μm for the outer divertor. Strikingly, these orderings coincide with the thickness of deposits found locally on the divertor: the exposed surfaces of high field side monoblocks are covered with several tens of μm tungsten deposits, while on the lower field side, few μm thin tungsten deposits are only found on the magnetically shadowed parts of monoblocks. The strong impact of those deposits on WEST operation, namely perturbation of surface temperature measurement with infra-red thermography, and the emission of flakes causing radiative perturbation of the confined plasma, calls for anticipating similar issues in ITER. In particular, the start of research operation shall consider the definition of a divertor erosion budget in order to anticipate the formation of deleterious deposits.
在一次 L 模式高通量活动中对 WEST 等离子体主要部件的钨毛侵蚀情况进行的调查
2023 年,在西部地区新安装的由热核实验堆级单体组成的主动冷却钨岔流器上进行了首次高通量活动。活动包括在附加岔流器条件下重复 60 秒长的氘 L 模式脉冲,等离子体暴露时间累计超过 10000 秒。在外侧撞击点区域达到了约 5⋅1026 m-2 的最大氘通量,代表了 ITER 的几个高性能脉冲。从可见光谱推断出的钨侵蚀总量显示,等离子体侵蚀最严重的部分是内岔道靶,侵蚀率是外岔道靶的十倍。距离等离子体几厘米的外侧中平面钨凸起显示的总侵蚀率比外侧分流器低两倍。我们的结论是,外侧中平面凸块对钨的远距离迁移和沉积到下分流器上的贡献微乎其微。内侧分流器上的累积总侵蚀率可转化为约 20μm 的有效总侵蚀厚度,而外侧分流器上的有效总侵蚀厚度约为 2μm。令人吃惊的是,这些顺序与分流器上局部沉积物的厚度相吻合:高磁场侧单块的裸露表面覆盖着几十微米的钨沉积物,而在低磁场侧,只有在单块的磁影部分才会发现几微米薄的钨沉积物。这些沉积物对 WEST 运行有很大影响,即对红外热成像表面温度测量的干扰,以及薄片发射对封闭等离子体造成的辐射扰动,因此需要对 ITER 中的类似问题进行预测。特别是,研究工作的开始应考虑确定分流器侵蚀预算,以预测有害沉积物的形成。
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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