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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.

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BibTeXRIS

Mata Cruz, Angelica. 2022-05-05. Radiation Damage Calculation Methodology. https://doi.org/10.2172/1866790

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36 MATERIALS SCIENCE↗