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首页> 外文会议>Symposium on Fusion Engineering >Modification of the NSTX-U outboard and Inboard Divertor tiles for the protection of the PF-1C coils
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Modification of the NSTX-U outboard and Inboard Divertor tiles for the protection of the PF-1C coils

机译：修改NSTX-U舷外和舷内分流器瓦片以保护PF-1C线圈

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The National Spherical Torus Experiment (NSTX) is a low aspect ratio, spherical torus (ST) located at the Princeton Plasma Physics Laboratory (PPPL). Its Centerstack Assembly (CSA) consists of the inner legs of the Toroidal Field windings, the Ohmic Heating solenoid, the inner Poloidal Field (PF) coils, thermal insulation, diagnostics, and an Inconel casing which forms the inner wall of the vacuum vessel boundary. The outside surface of this casing is protected from the heat loads by a layer of Plasma Facing Components (PFCs), in this case, a combination of ATJ and POCO TM graphite. The CSA is electrically isolated from the outer, large major radius part of the vacuum chamber by ceramic insulators. The gaps at the top and bottom of the machine between the CSA and the outer vessel are known as the “Coaxial Helicity Injection (CHI) Gaps”. The PF-1C divertor coils are located in this region shadowed by the CHI gap, however, late in the design of the NSTX Upgrade PFCs, MHD equilibria were discovered which could direct field lines through these CHI gaps and onto the PF-1C stainless steel casings. This could result in thermal flux from the main plasma body to flow along the field lines directly onto the coil. Though the probability of such an event is low, the heat flux on the 0.125” thick stainless steel casing could damage the coil beneath, or in worst case, rupture the casing itself, resulting in an accidental vent of the vacuum vessel. By extending downward the overhanging edge of the row 1 PFCs on the Outboard Divertor (OBD) and the Inboard Divertor (IBD) and by increasing their outermost radii, effectively narrowing the CHI gap, this should provide significant protection to the PF-1C casing.
机译：美国国家球形圆环实验（NSTX）是一种低纵横比的球形圆环（ST），位于普林斯顿等离子体物理实验室（PPPL）。它的中心组件（CSA）包括环形场绕组的内支脚，欧姆加热螺线管，内极场（PF）线圈，绝热层，诊断层和Inconel外壳，它们构成了真空容器边界的内壁。外壳的外表面通过一层等离子体面对部件（PFC）（在这种情况下为ATJ和POCO TM石墨的组合）来保护免受热负荷。 CSA通过陶瓷绝缘体与真空室的大外径外半径部分电隔离。 CSA和外部容器之间的机器顶部和底部的间隙称为“同轴螺旋注射（CHI）间隙”。 PF-1C分流器线圈位于被CHI间隙遮挡的区域，但是，在NSTX升级PFC的设计后期，发现了MHD平衡，可以将磁场线引导通过这些CHI间隙到达PF-1C不锈钢肠衣。这可能导致来自主等离子体主体的热通量沿着磁力线直接流到线圈上。尽管发生这种情况的可能性很小，但0.125英寸厚的不锈钢外壳上的热通量可能会损坏下面的线圈，或者在最坏的情况下，会使外壳本身破裂，从而导致真空容器意外排气。通过向下扩展舷外分流器（OBD）和舷内分流器（IBD）上第1行PFC的伸出边缘并增加其最外半径，有效地缩小CHI间隙，这将为PF-1C机壳提供重要保护。

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