Mechanical Characterization of Neutron Irradiated Tungsten

September 10, 2025

The plasma facing components (PFCs) in the ARC fusion power plant will need to
withstand significant heat, particle, and the neutron fluxes over their lifetime. CFS is
evaluating tungsten (W) based materials for ARC PFCs. An inherent property of W is that it
has a ductile to brittle transition temperature (DBTT) above which W deforms in a ductile
manner and below which W fails in a brittle manner. The DBTT of a W based PFC may be
affected by neutron irradiation. Characterization of the neutron irradiation effects of W and
W alloys on DBTT is thereby a key design input. Oak Ridge National Laboratory (ORNL) has
performed neutron irradiation of W materials for years, and there are numerous previously
irradiated and untested samples currently in storage at ORNL. This project will perform
tests on these already irradiated materials, allowing data gathering years earlier from what
could be achieved with a new irradiation campaign.