A reconstruction method is developed for recovering pin burnup characteristics from fuel cycle calculations performed in hexagonal-z geometry using the nodal diffusion option of the DIF3D/REBUS-3 code system. Intranodal distributions of group fluxes, nuclide densities, power density, burnup, and fluence are efficiently computed using polynomial shapes constrained to satisfy nodal information. The accuracy of the method is tested by performing several fast reactor numerical benchmark calculations and by comparing predicted local burnups with values measured for experimental assemblies in the Experimental Breeder Reactor II. The results indicate that the reconstruction methods are quite accurate yielding maximum errors in power and nuclide densities that are <2% for driver assemblies and typically <5% for blanket assemblies.