DIII-D真空容器保护系统升级

M. Hollerbach, R. Lee, J.P. Smith, P. Taylor
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引用次数: 3

摘要

通用原子公司DIII-D托卡马克装甲防护系统的升级已经完成。升级包括外墙和导流器气体挡板的单层石墨砖,并清洁现有的地板、天花板和内墙瓷砖,以去除瓷砖表面沉积的杂质层。新瓷砖取代了用作中性光束穿透的局部装甲的石墨瓷砖,三个石墨极向后备限制带,以及各种铬镍铁合金保护瓷砖。瓷砖总数从1636块增加到3200块,相应的船只覆盖率从40%增加到90%。为了容纳与外墙砖平行安装的冷凝泵,在外墙和偏置导流环之间安装了一个新的、石墨铠装的、环形连续的气体挡板。为了消除等离子体中的铜源,GRAFOIL垫片取代了以前用作惯性冷却瓦与血管壁之间的热传递界面的铜毡金属垫片。GRAFOIL是一种来自联合碳化物公司(Union Carbide, Inc.)的可剥离的柔性石墨材料,用于每个瓷砖与血管壁之间,以及每个瓷砖与其固定硬件之间。进行测试以确定GRAFOIL材料的机械顺应性、导热性和真空特性。为了进一步减少暴露在等离子体中的高z材料的数量,对现有的1636块石墨瓦进行了识别、去除和喷砂,以消除沉积的薄层金属,包括镍、铬和钼。在进行任何加工之前,对选定的一组瓷砖进行放射性测试,包括氚污染。以37 /spl μ m碳化硼粉为爆破介质,干氮为推进剂,在负压爆破柜中对瓦片进行磨砂爆破。在每个瓷砖表面去除30 ~ 50 μ亩/米厚的层。在重新安装之前,在超声波酒精浴中清洗瓷砖并真空烘烤至1000/spl℃。在1992年8月至1993年1月期间安装了石墨装甲和气体挡板,并对瓦片进行了喷砂。总结了新型装甲系统的初步作战经验。
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Upgrade of the DIII-D vacuum vessel protection system
An upgrade of the General Atomics DIII-D tokamak armor protection system has been completed. The upgrade consisted of armoring the outer wall and the divertor gas baffle with monolithic graphite tiles and cleaning the existing floor, ceiling, and inner wall tiles to remove any deposited impurity layer from the tile surfaces. The new tiles replace the graphite tiles used as local armor for neutral beam shine through, three graphite poloidal back-up limiter bands, and miscellaneous Inconel protection tiles. The total number of tiles increased from 1636 to 3200 and corresponding vessel coverage from 40% to 90%. A new, graphite armored, toroidally continuous, gas baffle between the outer wall and the biased divertor ring was installed in order to accommodate the cryocondensation pump that was installed in parallel with the outer wall tiles. To eliminate a source of copper in the plasma, GRAFOIL gaskets replaced the copper felt metal gaskets previously used as a compliant heat transfer interface between the inertially cooled tiles and the vessel wall. GRAFOIL, an exfoliated, flexible graphite material from Union Carbide, Inc., was used between each tile and the vessel wall and also between each tile and its hold-down hardware. Testing was performed to determine the mechanical compliance, thermal conductance, and vacuum characteristics of the GRAFOIL material. To further decrease the quantity of high Z-materials exposed to the plasma, the 1636 existing graphite tiles were identified, removed, and grit blasted to eliminate a thin layer of deposited metals which included nickel, chromium, and molybdenum. Prior to any processing, a selected set of tiles was tested for radioactivity, including tritium contamination. The tiles were grit blasted in a negative-pressure blasting cabinet using 37 /spl mu/m boron carbide powder as the blast media and dry nitrogen as the propellant. A 30 to 50 /spl mu/m-thick layer was removed from the surfaces of each tile. The tiles were cleaned in an ultrasonic alcohol bath and vacuum baked to 1000/spl deg/C prior to reinstallation. The installation of the graphite armor and gas baffle and the grit blasting of the tiles was performed in August 1992 through January 1993. Initial operational experience with the new armor system is summarized.
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Application of sidestream recycle to the separation of hydrogen isotopes by cryogenic distillation Repair of poloidal field magnets on Alcator C-Mod Beam species mix as a function of DIII-D neutral beam ion source operation parameters Design of the TPX limiter and armor components Design, control and operation of the vacuum and gas systems for Alcator C-Mod
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