Although　tungsten　is　considered　as　one　of　the　primary　candidates　for　plasma-facing　material　(PFM)　in　future　fusion　reactors,　blistering　induced　by　plasma　irradiation　adversely　affects　fusion　reactors.　To　overcome　blis-tering,　in　this　study,　we　proposed　an　approach　to　reduce　the　blistering　by　releasing　hydrogen　or　helium　(H/He)　through　the　grooved　surfaces　of　PFM.　In　order　to　verify　the　feasibility　of　this　approach　and　the　effectiveness　of　the　transverse　release　of　H/He,　the　deep　grooves　as　the　channel　simulants　on　the　tungsten　surface　were　fabri-cated　with　different　spacing　using　focused　ion　beam　(FIB).　The　result　of　helium　irradiation　shows　that　the　presence　of　grooved　surfaces　can　reduce　blisters　and　inhibit　the　rapid　growth　of　He　blisters.　In　addition,　the　blistering　reduced　significantly　with　decreasing　groove　spacing,　especially　when　the　groove　spacing　is　less　than　2　mu　m.　In　addition,　He-induced　blistering　shows　obvious　crystal　orientation　dependence,　and　the　(001)　surface　shows　the　most　serious　radiation　damage.