Surface erosion and modification of toughened, fine-grained, recrystallized tungsten exposed to TEXTOR edge plasma

Surface erosion and modification of toughened, fine-grained, recrystallized tungsten exposed to TEXTOR edge plasma
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DOI:
10.1088/0031-8949/2014/t159/014038
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发表时间:
2014-04
期刊:
影响因子:
2.9
通讯作者:
Y. Ueda;M. Oya;Y. Hamaji;H. T. Lee;H. Kurishita;Y. Torikai;N. Yoshida;A. Kreter;J. Coenen;A. Litnovsky;V. Philipps
Y. Ueda;M. Oya;Y. Hamaji;H. T. Lee;H. Kurishita;Y. Torikai;N. Yoshida;A. Kreter;J. Coenen;A. Litnovsky;V. Philipps
中科院分区:
物理与天体物理3区
文献类型:
--
作者:
Y. Ueda;M. Oya;Y. Hamaji;H. T. Lee;H. Kurishita;Y. Torikai;N. Yoshida;A. Kreter;J. Coenen;A. Litnovsky;V. Philipps

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为了评估增韧、细晶、再结晶(TFGR)-W对托克马克边缘等离子体环境的适用性,两个TFGR-W样本(TFGR-W 1.1wt%TiC和TFGR-W 3.3wt%TaC)通过限制器锁定系统暴露于TEXTOR托克马克中的31次相同的欧姆放电。最高表面温度达到约1300 °C。在这些温度条件下,两种TFGR-W的整体微观结构和弥散体分布保持完整,表明这些TFGR-W钨材料在这些等离子体加载条件下具有足够的稳定性。在高于1150 °C的等离子体暴露下,表面上的TiC分散体的侵蚀增强,而对于TaC分散体没有观察到这种增强的侵蚀,这可能是由于Ta的熔化温度高于Ti。
In order to evaluate the applicability of toughened, fine-grained, recrystallized (TFGR)-W to tokamak edge plasma environment, two TFGR-W specimens (TFGR-W 1.1wt%TiC and TFGR-W 3.3wt%TaC) were exposed to 31 identical ohmic discharges in the TEXTOR tokamak by means of a limiter lock system. The highest surface temperature reached was about 1300 °C. Under these temperature conditions, the bulk microstructure and dispersoids distribution of both TFGR-W remained intact, suggesting that these TFGR-W tungsten materials have sufficient stability under these plasma loading conditions. The erosion of TiC dispersoids on the surface was enhanced by plasma exposure above 1150 °C, while such enhanced erosion was not observed for TaC dispersoids probably due to the higher melting temperature of Ta than Ti.