Three-Stage Adjustment of Fluences, Transport Parameters and Damage Parameters in Reactor Vessels

The adjustment of neutron-fluence spectra at dosimetry surveillance and vessel positions and of the neutron cross sections (parameters) used to calculate them may be carried out in separate steps, provided the dosimetry and the neutron-transport parameters can be appropriately partitioned. We present the prescriptions for carrying out these steps. The purpose is to allow the use of widely available least-squares adjustment codes as modules of a consistent and comprehensive package for the adjustment of all relevant quantities in reactor dosimetry analyses.