Solute-point defect interactions, coupled ...
Type de document :
Article dans une revue scientifique: Article original
URL permanente :
Titre :
Solute-point defect interactions, coupled diffusion, and radiation-induced segregation in fcc nickel
Auteur(s) :
Toijer, E. [Auteur]
Messina, L. [Auteur]
Domain, C. [Auteur]
Vidal, J. [Auteur]
Becquart, C. S. [Auteur]
Olsson, P. [Auteur]
Messina, L. [Auteur]
Domain, C. [Auteur]
Vidal, J. [Auteur]
Becquart, C. S. [Auteur]
Olsson, P. [Auteur]
Titre de la revue :
Physical Review Materials
Nom court de la revue :
Phys. Rev. Materials
Numéro :
5
Éditeur :
American Physical Society (APS)
Date de publication :
2021-01-19
ISSN :
2475-9953
Résumé en anglais : [en]
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 ...
Lire la suite >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 solutedefect 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 alloysLire moins >
Lire la suite >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 solutedefect 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 alloysLire moins >
Langue :
Anglais
Comité de lecture :
Oui
Audience :
Non spécifiée
Établissement(s) :
Université de Lille
CNRS
INRA
ENSCL
CNRS
INRA
ENSCL
Collections :
Équipe(s) de recherche :
Métallurgie Physique et Génie des Matériaux
Date de dépôt :
2021-01-20T10:09:10Z
Fichiers
- Toijer_PRM_2021.pdf
- Version éditeur
- Accès libre
- Accéder au document