Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up


	Elementary cell of reactor core with radius Rel=2,46 cm for the determination of temperature field: 1 – coolant channel Rcc = 1.05 cm; 2 – nuclear fuel channel Rnf = 0.63 cm

Part of: Bulakh OI, Kostylev OK, Nesterov VN, Cherdizov EK (2019) Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up. Nuclear Energy and Technology 5(4): 289-295. https://doi.org/10.3897/nucet.5.48391