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


	Map of GT-MHR reactor core: white – fuel assemblies after irradiation during the burnup cycle; gray – fresh fuel assemblies; graphite reflector at the periphery and in the center

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