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Brazing Technology For Plasma Facing Components In Nuclear Fusion Applications Using Low And Graded CTE Interlayers

机译:使用低分级CTE中间层间核融合应用核融合应用的等离子体钎焊技术

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In Plasma Facing Components (PFCs) for nuclear fusion reactors, the protective material, carbon based or tungsten, has to be joined to the copper alloy heat sink for optimum heat transfer. High temperature vacuum brazing is a possible joining process as long as a proper interlayer is introduced to mitigate the residual stresses due to the mismatch of thermal expansion coefficient (CTE). Pure copper can act as plastic compliant layer, however for carbon based materials a proper structuring of the joining surface is necessary to meet the thermal fatigue lifetime requirements. In this work pure molybdenum and tungsten/copper Metal Matrix Composites (W-wires in Cu-matrix) interlayers have been studied as alternative to pure copper for carbon based protective materials in flat tile configuration. Finite element simulations of the brazing process have been performed to evaluate the expected residual stress reduction near the metal-carbon interface. In fact it has been demonstrated that stiff low CTE interlayers can shift the peak stresses from the weak carbon-metal interface to the strongest metal-metal one. Relevant samples have been manufactured and subjected to preliminary metallographic and thermal shock tests. Results obtained so far are encouraging and active cooled mock-ups are being prepared for high heat flux testing. Research work is in progress as regards monoblock configuration with both Wf/Cu MMC and graded Cu/W plasma sprayed and HIPped layers.
机译:在核熔化反应器的等离子体面向部件(PFC)中,保护材料,基于碳或钨必须连接到铜合金散热器以进行最佳热传递。高温真空钎焊是一种可能的连接过程,只要引入适当的中间层以减轻由于热膨胀系数(CTE)不匹配而减轻残余应力。纯铜可以充当塑料柔顺层,然而,对于基于碳的材料,适当的连接表面结构是满足热疲劳寿命要求的必要条件。在这项工作中,已经研究了纯钼和铜金属基质复合材料(Cu-Matrix中的W线)中间层作为诸如扁平瓷砖配置中基于碳的保护材料的纯铜替代。已经进行了有限元模拟钎焊过程以评估金属 - 碳界面附近的预期残余应力减少。实际上已经证明,硬质低CTE中间层可以将峰值应力从弱碳金属界面转移到最强的金属金属。已制造相关样品并进行初步金相和热冲击试验。到目前为止所获得的结果是鼓励和活性冷却模拟,用于高热通量测试。关于MonoBlock配置,通过WF / Cu MMC和渐变的Cu / W等离子体喷涂和折叠层,研究工作正在进行。

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