Joint ICTP-IAEA Workshop on Radiation Damage in Nuclear Systems: from Bohr to Young

This two-week workshop provides early-stage career researchers with a quantitative understanding of the impact of radiation damage on materials for existing fission and proposed fusion reactors. The emphasis is on the conceptual progression of theoretical and experimental techniques across spatial and time scales from atomistic descriptions to the macroscopic behaviour of bulk material.

This Workshop will be held at the Abdus Salam International Centre for Theoretical Physics in Trieste, Italy from 11 – 22 May 2020. It assists Ph.D. students and early-career researchers in developing a quantitative understanding of the impact of radiation damage on materials, both for existing fission and proposed fusion reactors. There is an emphasis on the conceptual progression of theoretical and experimental techniques across spatial and temporal scales from atomistic descriptions to the macroscopic behaviour of bulk material. The lecture topics cover properties of irradiated material, irradiation effects beyond primary damage, prediction and modelling of material behavior under irradiation, multi-scale modelling of defects, evolution of surfaces, effect of neutron and surrogate radiation of fusion-relevant materials, high-entropy alloys in nuclear materials applications, hydrogen isotope deposition, retention and permeation.

Topics:

•    Irradiated material: defect production and damage metrics
•    Dose-rate, damage energies, atomic displacement
•    Neutron-induced defects: transmutation, activation, depletion
•    Nuclear kinematics
•    Primary damage and beyond: cascades, voids, swelling
•    Correlation and prediction of material behaviour under irradiation
•    Paradigms for irradiation testing
•    Ion irradiation as a proxy for neutrons
•    Multiscale modelling of defects in nuclear materials
•    Evolution of surfaces under irradiation
•    The effect of neutron and surrogate radiation on the properties of fusion-relevant materials
•    Prospects for high-entropy alloys in nuclear materials applications
•    Hydrogen isotope deposition, trapping and permeation

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