Tungsten(W)is the most promising candidate for plasma facing material(PFM)in fusion reactors.However,the high ductile-brittle transition temperature(DBTT)and low ductility at low temperatures limit the lifetime of W-PFM.It has been reported that the addition of vanadium(V)in W constrains the grain growth and improves the relative density and mechanical properties [1].Nevertheless,little is known about the performances of W-V alloys under fusion relevant plasma conditions.The aim of this work is to investigate the surface modification and deuterium(D)retention in W-V alloys exposed to D plasmas.