A method of manufacturing a pelletized nuclear ceramic fuel, including preparation of uranium dioxide moulding powder with or without an addition of concentrated uranium oxide, pressing the moulding powder into pressed pellets and sintering the pressed pellets in a reducing atmosphere, wherein uranium dioxide powder is utilized as a raw material for the preparation of the uranium dioxide moulding powder, the uranium dioxide powder having a proportion of oxygen to uranium equal to:
- 2.37±0.04, and the uranium dioxide powder being preliminarily obtained by heating a ceramic grade uranium dioxide powder in air.