Standard integral measurement facilities

The usefulness of integral measurements in standard and reference neutron fields is examined in terms of the validation of microscopic differential-energy neutron fission cross section standards needed for fission reactor technology. This synthesis encompasses a summary description of the identified neutron fields and of the status of their spectral characterization, discussion of the corrections and uncertainties involved in such experiments, and an appraisal of the accuracy of integral fission cross sections, in particular in the light of interlaboratory comparisons. The significance of such integral measurements to the testing and improvement of evaluated nuclear data is illustrated by a limited confrontation with the ENDF/B IV cross section file. 4 figures, 4 tables