A new improved method was developed for calculating sensitivity coefficients of neutronics properties in light water reactor cells relative to infinite dilution cross sections. In our paper we have applied this method to calculate sensitivity coefficients and uncertainties of k-inf in UO_2 and MOX fueled PWR cells. Compared to the approximated method; the new method reduces sensitivity coefficients around resonance energy regions. We have checked the accuracy of the improved method by comparing with MCNP code and good agreement was found. The sensitivity coefficients evaluated by JENDL-4 and ENDF/B-Ⅵ are almost the same. For uncertainty we have compared the results with other published results, and show the causes of a large difference.
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