Abstract
A large number of swelling measurement data on the 0.1C–16Cr–15Ni–2Mo–2Mn–Ti–Si austenitic steel used as a fuel cladding at temperatures 640–870 К in the BN-600 fast reactor were analyzed. It was found that within irradiation temperatures 690–830 К a steady-state swelling dose rate was from 0.45%/dpa to 1.1%/dpa. By the statistical model of point defect migration for the 0.1C–16Cr–15Ni–2Mo–2Mn–Ti–S steel the dependence of the steady-state swelling rate on the irradiation temperature and displacement rate was calculated. The calculation data were consistent with the experimental data.
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