Actinide targets for neutron cross section measurements

The Advanced Fuel Cycle Initiative (AFCI) and the Generation IV Reactor Initiative have demonstrated a lack of detailed neutron cross sections for certain 'minor' actinides. For some closed-fuel-cycle reactor designs more than 50% of reactivity will, at some point, be derived from 'minor' actinides that currently have poorly known or in some cases not measured (n,γ) and (n,f) cross sections. Using a combination of resurrected techniques and new developments, we have made a series of targets including highly enriched 239Pu, 240Pu, and 242Pu. Thus far, we have electrodeposited these actinide targets. The chemical purification and electodeposition techniques will be described. (author)