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Recent RD activities on plasma facing components at JAERI

机译:Jaeri等离子面向组件的最新研发活动

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Plasma Facing Components will be exposed to severe heat loads during the normal operation, and will severely be eroded by evaporation and particle emission during disruptions in next generation fusion devices such as International Thermonuclear Experimental Reactor (ITER). In this paper, we present recent major R&D topics on plasma facing components (PFCs) at JAERI as follows; (1) thermal cycling experiments on a 1 m long divertor mock-up, (2) disruption simulation tests on B/sub 4/C doped CFCs and tungsten, (3) tensile and bending tests of beryllium/copper alloy duplex structures.
机译:在正常操作期间,等离子体面对部件将暴露于严重的热负荷,并且在国际热核实验反应器(浸泡)中的下一代融合装置中的中断期间,蒸发和颗粒发射将严重侵蚀。在本文中,我们在JAERI的等离子体面向组件(PFC)上的近期主要研发主题如下; (1)在1米长的偏移器模拟上的热循环实验,(2)B / SUB 4 / C掺杂CFCs和钨的破坏模拟试验,(3)铍/铜合金双相结构的拉伸和弯曲试验。

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