Cladding inner surface structure and damage: a), b) – fuel rod No. 1 (standard technology) Тirr. = 575 °C; c), d) – fuel rod No. 2 (standard technology) Тirr. = 595 °C; e), f) – fuel rod No. 3 (heated up to 1060 °C) Тirr. = 595 °C; g), h) – fuel rod No. 4 (heated up to 1180 °C) Тirr. = 570 °C; i), j) – fuel rod No. 5 (heated up to 1180 °C) Тirr. = 540 °C.

 
 
  Part of: Shemyakin VN, Kinev EA, Kozlov AV, Portnykh IA, Panchenko VL, Evseev MV (2019) Analyzing the causes for the dispersion of the fast reactor spent fuel rod cladding properties*. Nuclear Energy and Technology 5(4): 323-329. https://doi.org/10.3897/nucet.5.48423