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Overview of bore tools robot for nuclear fusion reactor maintenance

机译:核融合反应器维护的钻孔工具机器人概述

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Because of the radiation levels preventing direct, hands-on access to the machine components, maintenance work on ITER fusion experimental reactor will require the use of Remote Handling (RH) techniques. In particular, the replacement of components such as divertor and blanket modules will require the use of remote cutting, welding and Non Destructive Testing (NDT) of water cooling pipes. During the engineering design phase of ITER, a significant effort was done to develop Bore Tools Systems (BTS) for the remote maintenance. The results of previous work is here presented and new tooling solutions, in particular for use on the divertor maintenance, are discussed. The ITER First Wall (FW) assembly consists of 54 divertor cassettes located at the bottom of the Vacuum Vessel (VV) and 500 blanket modules to cover the entire Tokamak F.W.. Each of them is mechanically locked to the VV and connected to two water cooling pipes. Due to the need to replace the eroded plasma facing components (PFC's), theses components require to be periodically removed and re-installed from/into the VV. This operation requires, among others, the cutting, re-welding and inspection of hundreds of cooling pipes. The ITER machine geometry imposes severe geometrical constraints on the components which in turn affect the pipe tooling design and maintenance access. Therefore, a BTS technology, being more compact, has been selected. Commercially available tools have been considered but found not suitable for this application. A new set of pipe tools has been designed, developed and finally validated through a comprehensive R&D program. The program included parametric studies to assess the cutting, welding and NDT processes, with also tools deployment test inside 4" diameter pipes (316L) with 400 mm bend radius. This was achieved by developing a new, modular type, tool deployable system. This system is able to negotiate the various pipe bends and to overcome the friction forces generated during the tool system progress inside the pipe. The tests included the demonstration of pipe alignment prior to welding, which requires to generated high forces in-pipe, and also tools rescue in case of failure. While additional tests may be required, the initial development program indicates that the proposed bore tool system is a viable solution for the maintenance of ITER.
机译:由于防辐射水平防止直接,实践对机器组件的访问,磨料融合实验反应堆的维护工作将需要使用远程处理(RH)技术。特别地,更换诸如VERERTOR和毯子模块的部件将需要使用水冷管的远程切割,焊接和非破坏性测试(NDT)。在ITER的工程设计阶段,完成了大量的努力来开发用于远程维护的钻孔工具系统(BTS)。讨论了以前的工作的结果,并讨论了新的工具解决方案,特别是用于转移器维护的新工具解决方案。 ITER第一壁(FW)组件由位于真空容器(VV)底部的54隅孔盒组成,500个橡皮布模块,以覆盖整个TOKAMAK FW。它们中的每一个都机械地锁定到VV并连接到两个水冷却管子。由于需要更换侵蚀的等离子体面对部件(PFC),因此需要定期移除并将其从/进入VV的组件。该操作需要,其中切割,重新焊接和数百个冷却管的检查。 ITER机器几何形状对部件施加严重的几何约束,反过来影响管道工具设计和维护访问。因此,已经选择了BTS技术,更紧凑。已考虑市售工具,但发现不适合该应用。通过全面的研发计划设计,开发了一套新的管工具,并最终验证。该程序包括参数化研究,以评估切割,焊接和NDT工艺,还具有400mm弯曲半径的4“直径管道(316L)的工具部署测试。这是通过开发新的模块化型工具可部署系统来实现的。这个系统能够协商各种管道弯曲并克服在管道内部进展过程中产生的摩擦力。测试包括在焊接之前的管道对准的演示,这需要产生高力的管道,以及工具在发生故障时救援。虽然可能需要额外的测试,但初始开发程序表明所提出的钻孔工具系统是维护迭代的可行解决方案。

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