Fuel　cladding　tubes　of　nuclear　power　plants　are　operated　at　high　temperatures.　Creep　behavior　is　therefore　a　crucial　factor　during　the　design　and　safety　assessment　of　fuel　cladding　tubes.　In　this　study,　small　punch　creep　tests　(SPCTs)　were　conducted　for　tube　specimens　to　examine　the　creep　behavior　of　FeCrAl　fuel　cladding　tubes.　According　to　Chakrabarty＇s　membrane　stretching　theory　and　finite　element　simulation　results,　specimen　shape　had　a　negligible　influence　on　the　equivalent　uniaxial　creep　stress　and　minimum　creep　strain　rate.　Therefore,　the　calculation　equations　of　equivalent　uniaxial　creep　stress　and　creep　strain　of　plate　specimens　were　directly　used　for　tube　specimens.　When　the　lower　die　round　radius　was　0.2　mm,　its　effect　on　the　calculated　creep　stress　was　within　5%,　and　it　was　negligible　for　the　calculated　minimum　creep　strain　rate.　The　power　law　creep　model　of　the　FeCrAl　fuel　cladding　tube　was　obtained　based　on　the　test　results　of　SPCT　using　tube　specimens.