The IRDF2002 dosimetry cross section data are processed into very fine energy groups and added to the detector response library for the Monte Carlo code MCBEND. The IRDF2002 covariances are processed into broad groups to form a MCBEND detector covariance library. A number of benchmark experiments are analysed using MCBEND with both IRDF2002 and IRDF90 data and the results compared. Uncertainties due to material and detector cross sections are calculated automatically. The results demonstrate that the IRDF2002 115In(n,n')115mIn dosimetry cross sections give improved agreement between calculation and measurement in an iron benchmark and that use of IRDF2002 data allows straightforward, explicit and accurate calculation of single resonance detector reaction-rates, e.g., 197Au(n,γ)198Au.