Abstract
To improve the corrosion resistance of cladding tubes used in advanced nuclear reactors such as lead fast reactor (LFR), sodium-cooled fast reactor (SFR), and super-critical water-cooled reactor (SCWR), 10Cr1SiY ferrite/martensitic (F/M) cladding tubes with 6.00 mm outer diameter, 0.5 mm wall thickness and 285–297 cm length were fabricated by cold-rolling, annealing, and designed normalizing and tempering (N&T) treatment before the last cold-rolling. The results showed a precise dimension along the tubes with an ovality lower than 1%. After 18.6% cold-rolling, isotropic structure with less differential of microstructure between the rolling section and cross section was observed by electron backscattered diffraction (EBSD) analysis. The slight rotation of martensite laths and formation of dislocation cells near ferrite borders would take responsibility for the phenomenon based on the coincidence site lattice (CSL) boundaries and orientation distribution function (ODF) plots. Ultimate tensile strengths (UTS) are 853 and 200 MPa while elongations are 7.8% and 27.5% for the 10Cr1SiY tube at room temperature (RT) and 700℃, respectively. The relationship between tube fracture surface and necking was found. A higher fraction of inner segment means more serious necking during the tensile test, which explains the higher total elongation but lower uniform elongation at 700℃.
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