Z.J. Bergstrom , J. Henry , A. Basaran , C. Monton , T. Abrams , B. Grierson
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Hydrogen interactions in solution-strengthened niobium-based alloys for direct internal recycling
Group 5 metals are promising candidates for hydrogen (H) separation due to their exceptionally high permeability. However, they are prone to fracture-failure caused by H-induced embrittlement which limits their application. First-principles calculations were used to assess the effect of alloying element density in niobium-tungsten (Nb-W), niobium-nickel (Nb-Ni), and niobium-iron (Nb-Fe) alloys on H solubility, diffusivity, and permeability. Ground state energy calculations were performed to assess the average heat of solution and nudged elastic band calculations were performed to assess migration barriers between adjacent H interstitial positions. Migration barriers were used to parameterize a kinetic Monte Carlo diffusion model. Results show diminished H solubility and diffusivity with increasing dopant concentration. H delocalization and enhanced trapping are observed for Ni and Fe dopants, resulting in dramatic reduction in diffusivity and permeability. Nb-W alloys show high permeability and no enhanced trapping, suggesting Nb-W alloys may reduce H-induced embrittlement of membranes in metal foil pumps (MFP).
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.