Study on tungsten materials highly relevant for a complicated irradiation environment in fusion reactors

研究了混合离子辐照和重复脉冲热负荷对纯W和抗中子辐照的TFGR-W的氢同位素保留和表面形貌变化的影响。对不同的分散体(TiC和TAC)进行了评价，以获得有价值的结果来改进其性能。TFGR-W是利用超塑性新开发的材料加工技术制备的，尺寸为ITER单块。

Effects of mixed ion irradiation and repeated pulse heat load on hydrogen isotope retention and surface morphology changes were studied for pure W and TFGR-W, which is known to be resistant to neutron irradiation. Evaluation of different dispersoids (TiC and TaC) was performed to obtain valuable results to modify its performance. TFGR-W with dimensions of ITER monoblocks was fabricated by a newly developed material processing technique using superplasticity.