When　cracks　are　detected　in　structural　components　of　nuclear　power　plants,　the　integrity　of　cracked　components　should　be　assessed　by　comparing　the　material　strength　with　the　crack　driving　force　(e.g.,　stress　intensity　factor　KI).　To　support　the　structural　integrity　assessment　of　nuclear　components　with　cracks,　several　fitness-for-service　(FFS)　codes　have　been　established　in　which　KI　solutions　are　provided　for　various　components　and　cracks.　For　nozzle　corner　cracks　in　reactor　pressure　vessels　(RPVs),　the　existing　KI　solutions　are　found　to　have　limitations　in　applications　because　of　the　complexity　of　nozzle　geometrical　configurations　and　stress　concentrations.　In　particular,　only　KI　solutions　at　the　deepest　point　of　the　nozzle　corner　crack　are　provided　in　the　FFS　codes　and　the　applicable　range　of　those　KI　solutions　is　not　clear.　Thus,　in　this　study,　three-dimensional　finite　element　analyses　(FEAs)　were　performed　to　develop　normalized　KI　solutions　for　a　wide　range　of　nozzle　corner　cracks,　with　the　objective　of　supporting　the　structural　integrity　assessment　of　RPV　nozzles.　The　RPV　inner　radius　to　thickness　ratio　Rv/tv　from　5　to　20,　nozzle　inner　radius　to　thickness　ratio　Rn/tn　from　1　to　5,　and　the　nozzle　inner　radius　to　RPV　inner　radius　ratio　Rn/Rv　from　0.025　to　0.25,　were　considered　in　the　FEAs.　The　KI　solutions　along　the　crack　front　of　nozzle　corner　cracks　with　the　normalized　crack　depth　a/te　from　0.1　to　0.6　(herein,　te　=　2·max(tv,　tn))　were　analyzed　with　a　fourth-order　polynomial　stress　distribution　applied　on　the　crack　face.　By　using　the　developed　KI　solutions　for　nozzle　corner　cracks,　several　application　examples　considering　internal　pressure　and　thermal　transient　are　also　presented　in　this　paper.　The　results　demonstrate　that　the　developed　KI　solutions　are　highly　useful　for　the　integrity　assessment　of　cracked　RPV　nozzles　under　diverse　loading　conditions.　©　2025　Elsevier　Ltd