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Tokamak Physics Experiment divertor design

机译:托卡马克物理实验偏滤器设计

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The Tokamak Physics Experiment (TPX) tokamak requires a symmetric up/down double-null divertor capable of operation with steady-state heat flux as high as 7.5 MW/m/sup 2/. The divertor is designed to operate in the radiative mode and employs a deep slot configuration with gas puffing lines to enhance radiative divertor operation. Pumping is provided by cryopumps that pump through eight vertical ports in the floor and ceiling of the vessel. The plasma facing surface is made of carbon-carbon composite blocks (macroblocks) bonded to multiple parallel copper tubes oriented vertically. Water flowing at 6 m/s is used, with the critical heat flux (CHF) margin improved by the use of enhanced heat transfer surfaces. In order to extend the operating period where hands on maintenance is allowed and to also reduce dismantling and disposal costs, the TPX design emphasizes the use of low activation materials. The primary materials used in the divertor are titanium, copper, and carbon-carbon composite. The low activation material selection and the planned physics operation will allow personnel access into the vacuum vessel for the first 2 years of operation. This 2-year period will allow final in-vessel checkout of the remote handling equipment. The remote handling system requires that all plasma facing components (PFCs) are configured as modular components of restricted dimensions with special provisions for lifting, alignment, mounting, attachment, and connection of cooling lines, and instrumentation and diagnostics services. Alignment of the plasma facing surface to the as-built magnetic field and to neighboring modules is critical to limit peak temperatures and limit carbon impurities in the plasma. Both local edge-to-edge and overall alignment of the divertor is accomplished using a machined alignment ring system. This ring system maintains the modules in a circular array and is adjusted during machine assembly to align with the as-built magnetic field. The macroblocks have 10 mm of carbon-carbon protection for the copper tubes, of which 7 mm is considered erosion allowance.
机译:Tokamak物理实验(TPX)Tokamak需要一种对称的上/向下双核置换器,其能够使用稳态热通量操作,高达7.5 mW / m / sup 2 /。转型器设计用于辐射模式,采用深槽配置,具有气体膨化线,以增强辐射偏移器操作。通过泵送泵送八个垂直端口的泵送,泵送泵送。等离子体面对表面由粘合到垂直定向的多个平行铜管的碳 - 碳复合块(宏块)制成。通过使用增强的传热表面,使用临界热通量(CHF)裕度而流动的水流。为了延长允许进行维护的操作期,并减少拆卸和处置成本,TPX设计强调使用低激活材料。转移器中使用的主要材料是钛,铜和碳复合材料。低激活材料选择和计划的物理操作将允许人员进入真空容器的前2年。这两个年期间将允许最终船舶结账遥控设备。远程处理系统要求所有等离子体面对部件(PFC)配置为具有限制尺寸的模块化部件,具有用于升降,对准,安装,附件和连接冷却管路的特殊规定,以及仪器和诊断服务。等离子体面对面的面对面的磁场和相邻模块的对准对于限制峰值温度和限制等离子体中的碳杂质至关重要。使用加工的对准环系统实现转栓的局部边缘到边缘和整体对准。该环系统将模块保持在圆形阵列中,并在机器组件期间调节以与磁场对齐。宏块对铜管具有10毫米碳 - 碳保护,其中7毫米被认为是腐蚀余量。

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