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

被引:19
作者
Toijer, E. [1 ]
Messina, L. [1 ,2 ]
Domain, C. [3 ]
Vidal, J. [3 ]
Becquart, C. S. [4 ]
Olsson, P. [1 ]
机构
[1] KTH Royal Inst Technol, Nucl Engn, SE-11421 Stockholm, Sweden
[2] CEA, IRESNE, DEC, DES, F-13108 Cadarache, St Paul Lez Dur, France
[3] EDF R&D, Dept Mat & Mech Components, F-77250 Moret Sur Loing, France
[4] Univ Lille, UMR 8207, Cent Lille, INRAE,CNRS,UMET Unite Mat & Transformat, F-59000 Lille, France
来源
PHYSICAL REVIEW MATERIALS | 2021年 / 5卷 / 01期
基金
瑞典研究理事会;
关键词
SELF-DIFFUSION; GRAIN-BOUNDARY; MULTICOMPONENT ALLOY; NI; EVOLUTION; MODEL; IRRADIATION; ELEMENTS; SILICON; COEFFICIENTS;
D O I
10.1103/PhysRevMaterials.5.013602
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
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.
引用
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页数:16
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