Modelling radiation damage effects on a bcc iron lattice containing phosphorous impurity atoms near symmetrical tilt boundaries
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference19 articles.
1. Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications
2. Irradiation-induced impurity segregation and ductile-to-brittle transition temperature shift in high chromium ferritic/martensitic steels
3. The role of irradiation-induced phosphorus segregation in the ductile-to-brittle transition temperature in ferritic steels
4. Grain boundary impurity segregation and neutron irradiation effects in ferritic alloys
5. Control of phosphorus inter-granular segregation in ferritic steels
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1. Effect of Grain Boundary on Diffusion of P in Alpha-Fe: A Molecular Dynamics Study;Frontiers in Physics;2019-07-12
2. Primary radiation damage of Fe-10%Cr models under uniaxial, biaxial, and hydrostatic pressure using MD simulation;Journal of Nuclear Materials;2018-10
3. Effects of grain boundaries on irradiation-induced defects in tungsten by molecular dynamics simulations;Journal of Iron and Steel Research International;2018-02
4. The interaction between atomic displacement cascades and tilt symmetrical grain boundaries in α-zirconium;Radiation Effects and Defects in Solids;2017-05-07
5. Evolution of displacement cascades in Fe–Cr structures with different [001] tilt grain boundaries;Radiation Effects and Defects in Solids;2017-01-19
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