Boron powder injection experiments in WEST with a fully actively cooled, ITER grade, tungsten divertor

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Materials and Energy Pub Date : 2024-08-20 DOI:10.1016/j.nme.2024.101724
K. Afonin , A. Gallo , R. Lunsford , S. Bose , Y. Marandet , P. Moreau , G. Bodner , H. Bufferand , G. Ciraolo , C. Desgranges , P. Devynck , A. Diallo , J. Gaspar , C. Guillemaut , R. Guirlet , J.P. Gunn , N. Fedorczak , Y. Corre , F. Nespoli , N. Rivals , E.A. Unterberg
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Abstract

Reactor relevant fusion devices will use tungsten (W) for their plasma facing components (PFCs) due to its thermomechanical properties and low tritium retention. However, W introduces high-Z impurities into the plasma, degrading its performance. Different wall conditioning methods have been developed to address this issue, including coating of W PFCs with layers of low-Z material. Wall conditioning by boron (B) powder injection using an impurity powder dropper (IPD) is being studied in WEST. Two series of experiments were conducted since the installation of the new ITER grade full W divertor. During the first series in 2023 ∼ 1 g of B powder was injected in total at a maximum rate of ∼ 58 mg/s, both of which are three times greater than respective values in the initial WEST powder injection experiments. The second series of experiments included injection of B and BN powders for comparison of their effects on plasma performance. The presence of an instantaneous conditioning effect is suggested by visible spectroscopy measurements of low-Z impurity lines and a rollover of total radiated power past an injection rate of ∼ 20 mg/s was observed. Presence of B coating layer formation is supported by the evolution of the average radiance of visible lines of B, W and oxygen (O). To understand B transport, an interpretative modeling workflow is employed, utilizing the SOLEDGE-EIRENE fluid boundary plasma code and the Dust Injection Simulator (DIS) code. Parameters like B perpendicular diffusivity and recycling coefficients are varied to match experimental results to see if the initial assumption of B sticking to the PFCs immediately after the contact with the wall is adequate for correctly modelling its distribution on the PFCs.

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利用完全主动冷却的热核聚变实验堆级钨分流器在 WEST 进行硼粉末注入实验
由于钨(W)的热机械特性和低氚保留率,反应堆相关聚变装置将使用钨(W)作为等离子体面组件(PFC)。然而,钨会在等离子体中引入高 Z 杂质,从而降低等离子体的性能。为了解决这个问题,已经开发出了不同的壁调节方法,包括在 W PFC 表面涂上一层低 Z 材料。目前,WEST 正在研究使用杂质滴粉器(IPD)注入硼(B)粉末进行壁调节的方法。自安装新的热核实验堆级全 W 分流器以来,进行了两个系列的实验。在 2023 年的第一个系列实验中,总共注入了 1 克 B 粉末,最大速率为 58 毫克/秒,这两个数值都比最初的 WEST 粉末注入实验中的相应数值高出三倍。第二系列实验包括注入 B 和 BN 粉末,以比较它们对等离子体性能的影响。低 Z 杂质线的可见光谱测量结果表明了瞬时调节效应的存在,并观察到总辐射功率在注入速率为 20 毫克/秒时发生了翻转。硼、钨和氧(O)可见光线平均辐射率的变化证明了硼涂层的形成。为了解硼的传输,利用 SOLEDGE-EIRENE 流体边界等离子体代码和粉尘注入模拟器(DIS)代码,采用了解释性建模工作流程。为了与实验结果相匹配,对 B 垂直扩散率和循环系数等参数进行了改变,以了解 B 在与壁接触后立即粘附在 PFC 上的初始假设是否足以正确模拟其在 PFC 上的分布。
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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.
期刊最新文献
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