[en] This report gives, with some editorial improvement, the contents of an invited paper, prepared for the IAEA Advisory Group Meeting on nuclear data for reactor dosimetry, held at Vienna, 13-17 November 1978. It describes the present status of the confrontation of measured cross section values averaged over a benchmark neutron spectrum, with the calculated values, derived from evaluated cross section data and the best available numerical benchmark spectrum data. Information is collected on three aspects of the comparison: the uncertainty in the average cross section values, the discrepancy between measured and calculated section values, and the consistency between measured and calculated values. Available numerical data are presented in a series of tables. The calculated average cross sections are mainly based on the ENDF/B-IV dosimetry file. It is planned to repeat and extend this study when new or more evaluated data become available