Parameter-free quantitative simulation of high-dose microstructure and hydrogen retention in ion-irradiated tungsten

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http://hdl.handle.net/10138/337096

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Mason , D R , Granberg , F , Boleininger , M , Schwarz-Selinger , T , Nordlund , K & Dudarev , S L 2021 , ' Parameter-free quantitative simulation of high-dose microstructure and hydrogen retention in ion-irradiated tungsten ' , Physical Review Materials , vol. 5 , no. 9 , 095403 . https://doi.org/10.1103/PhysRevMaterials.5.095403

Title: Parameter-free quantitative simulation of high-dose microstructure and hydrogen retention in ion-irradiated tungsten
Author: Mason, Daniel R.; Granberg, Fredric; Boleininger, Max; Schwarz-Selinger, Thomas; Nordlund, Kai; Dudarev, Sergei L.
Contributor organization: Department of Physics
Materials Physics
Helsinki Institute of Sustainability Science (HELSUS)
Helsinki Institute of Urban and Regional Studies (Urbaria)
Date: 2021-09-17
Language: eng
Number of pages: 13
Belongs to series: Physical Review Materials
ISSN: 2475-9953
DOI: https://doi.org/10.1103/PhysRevMaterials.5.095403
URI: http://hdl.handle.net/10138/337096
Abstract: Hydrogen isotopes are retained in plasma-facing fusion materials, triggering hydrogen embrittlement and changing tritium inventory as a function of exposure to neutron irradiation. But modeling highly damaged materials-exposed to over 0.1 displacements per atom (dpa)-where saturation of damage is often observed, is difficult because a microstructure containing high density of defects evolves nonlinearly as a function of dose. In this study we show how to determine the defect and hydrogen isotope content in tungsten exposed to high irradiation dose, using no adjustable or fitting parameters. First, we generate converged high dose (>1 dpa) microstructures, using a combination of the creation-relaxation algorithm and collision cascade simulations. Then we make robust estimates of vacancy and void regions using a modified Wigner-Seitz decomposition. The resulting estimates of the void surface area enable predicting the deuterium retention capacity of tungsten as a function of radiation exposure. The predictions are compared to 3He nuclear reaction analysis measurements of tungsten samples, self-irradiated at 290 K to different damage doses and exposed to low-energy deuterium plasma at 370 K. The theory gives an excellent match to the experimental data, with both model and experiment showing that 1.5-2.0 at.% deuterium is retained in irradiated tungsten in the limit of high dose.
Subject: KINETIC MONTE-CARLO
DEUTERIUM RETENTION
MOLECULAR-DYNAMICS
RADIATION-DAMAGE
CASCADE DAMAGE
DEFECT DENSITY
DISLOCATION
EVOLUTION
DIFFUSION
ALLOYS
114 Physical sciences
Peer reviewed: Yes
Usage restriction: openAccess
Self-archived version: publishedVersion


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