摘要
Tungsten (W) is a promising candidate for plasma-facing materials (PFMs) in fusion reactors owing to its excellent thermal conductivity, sputtering resistance, and low hydrogen isotope solubility [1]. W PFMs encounter the challenges of triple irradiations generated by high-heat loads;high-flux particles, including helium/deuterium (D)/tritium (T);and high-energy neutrons.
基金
supported by the National Natural Science Foundation of China(Grant No.51720105006)
the Science and Technology on Surface Physics and Chemistry Laboratory(Grant No.02020317)
