摘要
International thermonuclear experimental reactor(ITER),the largest tokamak device so far,will operate with a full-tungsten divertor to handle the steady heat fluxes of 10 MW m^(−2),the slow transients of 20 MW m^(−2)(~10 s),as well as the transient heat fluxes up to~GM m^(−2)(<1 ms).Currently,tungsten(W)is also foreseen as the most suitable plasma-facing material(PFM)for the first wall in demonstration(DEMO)and future fusion reactors,as well as the divertor.The wall material in future fusion reactors must fulfill the requirements of sufficient lifetime,negligible or small long-term retention of tritium(T)fuel and an acceptable neutron activation level in long-term operation,which are favorable for W walls.
