Recent Research in Neutron Dosimetry and Damage Analysis for Materials Irradiations

Abstract

Neutron fluence measurements and damage calculations are being routinely performed for fusion materials irradiations in fission reactors, at 14 MeV sources, and at high-energy accelerator neutron sources. Neutron activation cross sections are being developed for dosimetry at fission reactors, fusion reactors, and high-energy accelerator neutron sources. Integral and differential measurements are being combined to determine new cross sections and to adjust discrepant data. These data are needed to adequately define the neutron exposure and radiation damage in materials. The production of long-lived radioisotopes is being measured at 14 MeV for fusion reactors and reactions are being developed for plasma diagnostics. At high energies, spallation cross sections are being measured for dosimetry and damage analysis at accelerator neutron sources. Helium production cross sections are being tested and a new thermal helium effect has been discovered in copper similar to the well-known effect in nickel. Damage calculations are routinely provided by the SPECTER computer code and new calculations are being performed to extend our damage cross sections to higher energies for accelerator neutron sources and to include alloys and compounds.