DOE OSTI · 1866790
Radiation Damage Calculation Methodology
Abstract
This report outlines the consensus radiation damage calculation methodology used by the Neutronics Analysis Group at Idaho National Laboratory. This methodology includes calculation of radiation damage rates via the Monte Carlo N-Particle (MCNP) code, and calculation of radiation damage in mixed materials, such as alloys. A consistent method for calculating the average displacement threshold energy of a mixed material has been established by the Neutronics Analysis Group. No standard method currently exists to account for radiation damage caused by neutron-induced transmutations. Only one documented case addresses transmutation radiation damage in materials containing nickel, and that method was incorporated by the Neutronics Analysis Group into their radiation damage calculation methodology.
Explore related subjects
Keep this discovery
Explore connections, maps & timelines
Mata Cruz, Angelica. 2022-05-05. Radiation Damage Calculation Methodology. https://doi.org/10.2172/1866790
Cite the original work for its findings. Save a collection to share your selection of sources.