4.3 Article

Solute-point defect interactions, coupled diffusion, and radiation-induced segregation in fcc nickel

Journal

PHYSICAL REVIEW MATERIALS
Volume 5, Issue 1, Pages -

Publisher

AMER PHYSICAL SOC
DOI: 10.1103/PhysRevMaterials.5.013602

Keywords

-

Funding

  1. Euratom research and training program 2014-2018 [755269, 633053]
  2. Swedish Centre for Nuclear Technology (SKC)
  3. CINECA award under the ISCRA initiative
  4. Swedish Research Council [2016-07213]
  5. PRACE [project MORPHO (modeling radiation damage: characterization of elementary physical processes)] [2016153636]

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This study investigates radiation-induced segregation in face centered cubic Ni-X dilute binary alloys, examining the tendencies and effects of solutes during migration. The results show different segregation behaviors of solutes during radiation-induced migration, providing important insights into the kinetic properties of materials.
Radiation-induced segregation (RIS) of solutes in materials exposed to irradiation is a well-known problem. It affects the lifetime of nuclear reactor core components by favoring radiation-induced degradation phenomena such as hardening and embrittlement. In this work, RIS tendencies in face centered cubic (fcc) Ni-X (X = Cr, Fe, Ti, Mn, Si, P) dilute binary alloys are examined. The goal is to investigate the driving forces and kinetic mechanisms behind the experimentally observed segregation. By means of ab initio calculations, point-defect stabilities and interactions with solutes are determined, together with migration energies and attempt frequencies. Transport and diffusion coefficients are then calculated in a mean-field framework, to get a full picture of solute-defect kinetic coupling in the alloys. Results show that all solutes considered, with the exception of Cr, prefer vacancy-mediated over interstitial-mediated diffusion during both thermal and radiation-induced migration. Cr, on the other hand, preferentially migrates in a mixed-dumbbell configuration. P and Si are here shown to be enriched, and Fe and Mn to be depleted at sinks during irradiation of the material. Ti and Cr, on the other hand, display a crossover between enrichment at lower temperatures, and depletion in the higher temperature range. Results in this work are compared with previous studies in body centered cubic (bcc) Fe, and discussed in the context of RIS in austenitic alloys.

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