[en] The report describes the physical characteristics of a PWR fuel assembly. A model of the assembly is then defined, and a two-dimensional gamma-ray shielding code is applied to the model to calculate the dose rate from a bare fuel assembly. The results of the calculations are the dose rates from the assembly at points on the surface of the assembly, on spatial surfaces 1 m from a side and the end piece of the assembly, and on spatial surfaces 2 m from a side and the end piece of the assembly. Dose rates are calculated for as-generated mixed fission products and for a uniformly distributed ⁶⁰Co spike. Factors are given to account for the effect of decay on the dose rates