Distributions of tangential stresses on the fuel rod surface and velocity in the channel cross-section in the peripheral region of a model FA with displacers in the peripheral channels with a nominal geometry (a, b) and during a fuel lattice strain in the FA peripheral region (c, d).

  Part of: Kuzina YuA, Sorokin AP, Delnov VN, Denisova NA, Sorokin GA (2022) ´╗┐Thermohydraulic studies of alkali liquid metal coolants for justification of nuclear power facilities. Nuclear Energy and Technology 8(4): 281-288. https://doi.org/10.3897/nucet.8.96568