Abstract
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.
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