Selective　laser　melting　(SLM)　offers　unprecedented　advantages　in　manufacturing　complex　components　used　in　nuclear　reactors,　and　thus　has　promising　application　in　the　nuclear　power　industry.　The　compatibility　of　printed　materials　with　typical　reactor　coolant　should　be　carefully　investigated　as　the　printed　materials　possess　unique　microstructure　features　(e.g.　columnar　grain,　dislocation　cell　and　inclusion)　which　would　inevitably　affect　the　performance.　In　this　work,　the　stress　corrosion　cracking　(SCC)　susceptibility　of　selective　laser　melted　(SLMed)　304L　stainless　steel　(SS)　was　evaluated　in　high-temperature　hydrogenated　water　through　slow　strain　rate　tensile　test　and　compared　with　two　wrought　304　SSs.　Interestingly,　the　SLMed　304L　SS　showed　much　lower　SCC　susceptibility　than　the　two　wrought　304　SSs,　and　this　finding　was　mainly　ascribed　to　its　optimized　composition.　From　the　aspect　of　corrosion,　the　intergranular　oxidation　resistance　of　SLMed　304L　SS　is　significantly　improved　due　to　the　reduced　contents　of　Si　and　Mn.　In　addition,　the　high　dislocation　density　in　SLMed　304L　SS　can　accelerate　the　diffusion　of　solute　atoms,　thus　further　enhancing　the　resistance　to　intergranular　oxidation　and　promoting　the　precipitation　of　oxide　inside　the　crack　which　barricades　the　ingress　of　corrosive　media.　As　for　the　mechanical　aspect,　under　the　combined　effects　of　dislocation　cells　and　nano-oxide　inclusions,　the　SCC　initiation　can　be　alleviated　as　the　dislocation　motion　in　the　grain　matrix　is　hindered　and　planar　slip　is　suppressed.　Therefore,　the　optimized　chemical　composition　and　printed　microstructure　render　this　SLMed　304L　SS　more　resistant　to　SCC　initiation.　©　2022　Acta　Materialia　Inc.