On the consistency between integral and differential cross section data

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