Dependences of fluxes of thermal Фt and damaging Фd neutrons on the nuclear fuel burnup

  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.