† Corresponding author. E-mail:
Project supported by the National Natural Science Foundation of China (Grant No. U1867217), the National Science and Technology Major Project of the Ministry of Science and Technology of China (Grant No. 2019ZX06004009), and the China National Nuclear Corporation Centralized Research and Development Project (Grant No. FY18000120).
The migration of lanthanide fission products to cladding materials is recognized as one of the key causes of fuel–cladding chemical interaction (FCCI) in metallic fuels during operation. We have performed first-principles density functional theory calculations to investigate the segregation behavior of lanthanide fission products (La, Ce, Pr, and Nd) and their effects on the intergranular embrittlement at Σ3(111) tilt symmetric grain boundary (GB) in α-Fe. It is found that La and Ce atoms tend to reside at the first layer near the GB with segregation energies of −2.55 eV and −1.60 eV, respectively, while Pr and Nd atoms prefer to the core mirror plane of the GB with respective segregation energies of −1.41 eV and −1.50 eV. Our calculations also show that La, Ce, Pr, and Nd atoms all act as strong embrittlers with positive strengthening energies of 2.05 eV, 1.52 eV, 1.50 eV, and 1.64 eV, respectively, when located at their most stable sites. The embrittlement capability of four lanthanide elements can be determined by the atomic size and their magnetism characters. The present calculations are helpful for understanding the behavior of fission products La, Ce, Pr, and Nd in α-Fe.
In the generation IV international forum, the metallic fuels for the sodium-cooled fast breeder reactor, which have been studied for more than five decades with the documented performances, were brought under renewed focus.[1] The metallic fuel pin is mainly comprised of rod-shaped fuel alloy made of U–Zr or U–Pu–Zr, HT-9 steel cladding, and the fuel-to-clad gap filled with liquid sodium.[2] They have been used in the experimental breeder reactor II (EBR-II) and qualified up to a specific burnup of 10 at.%.[3] One of the major reasons for the limitation of higher burnup is fuel–cladding chemical interactions (FCCI), which occur at the fuel and cladding interface during irradiation.[2,4–7]
FCCI is complex, including fuel–cladding interaction (e.g., U–Fe) and the interactions among fission products containing a significant mount of lanthanides (Ln) and cladding (e.g., Ln–Fe). Among them, the greatest concern of FCCI is the lanthanide–cladding interaction, as lanthanides are observed to migrate fast in a fuel and diffuse rapidly into cladding (50–150 μm),[8] yielding intermetallic precipitation, phase changes, and melting.[9–11] The lanthanide interaction with clad affects the mechanical integrity of the cladding, and is deemed a long-term, high-burnup cause of the cladding failures. Actually, fission product segregation to the grain boundary (GB) is a prerequisite for the formation of a brittle intermetallic phase. The segregation behavior could produce a significant effect on the GB cohesion, therefore limiting the ductility of the metallic alloys. Thus, the segregation of fission products and their effects on GB in the cladding is of concern, and a fundamental knowledge of these processes is needed.
Impurities and alloy elements are generally aggregated at GB, which substantially affects the mechanical properties, primary ductility, fracture toughness, and strength of metallic materials. Extensive experimental and theoretical researches have been performed on their influence on GB cohesion. For instance, interstitial boron and substitutional Mo can enhance the GB strength in Fe alloys,[12,13] while H impurities weaken GB, which is one of the mechanisms of hydrogen embrittlement.[14] On the other hand, based on the Rice–Wang model,[15] first-principles density functional theory (DFT) calculations of intergranular cohesion in the presence of segregated impurities in Fe were pioneered by Krasko and Olson, followed by extensive calculations by Freeman, Olson, and co-workers.[16–18] They employed the full potential linearized augmented-plane-wave (FPLAPW) method to study several different impurities and alloying elements at Σ3(111) symmetrical tilt GB in Fe.[18] More recently, the projector augmented wave (PAW) approach was used to study the effects of impurities on the GB. To our knowledge, there are few ab initio calculations for lanthanides segregation and intergranular cohesion in Fe.
The reports of post irradiation examination (PIE) data of metallic fuels (U–Zr and U–Pu–Zr) irradiated in EBR-II reactor suggested that the major lanthanides diffusing into cladding were La, Ce, Pr, and Nd.[8,19] Symmetry Σ3(111) [110] GB is a typical high-angle GB with remarkable excess volume for body-centered cubic (bcc) iron. In this work, combining first-principles calculations and the Rice–Wang model, the preferential site, segregation energy, and embrittlement capability of the four lanthanides at the Σ3(111) [110] GB in α-Fe will be investigated. We organize the remainder of the paper as follows. In Section
Our first-principles DFT calculations were performed using the Vienna ab initio simulation package (VASP).[20–22] The interaction between valence electron and nuclei was obtained using the projector augmented wave (PAW) method.[23,24] The exchange and correlation terms in DFT method were treated with generalized gradient approximation (GGA) in the Perdew–Burke–Ernzerhof (PBE) form.[25] A conjugate gradient algorithm was used to relax the atomic positions to a local minimum in the total energy landscape. The cut-off energy for the plane wave basic set was 350 eV. For each system, geometry optimization could continue until the total energy of this system was converged to less than 10−4 eV. A 7 × 4 × 1 k-mesh in Monkhorst–Pack scheme replaced the integration over Brillouin zone in the following simulation.[26]
We selected the Σ3(111)[
In order to assess the tendency of the fission product to segregate to the GB from the bulk environment, the segregation energy of one X atom (X = La, Ce, Pr, and Nd) at GB is defined by
Since lanthanides La, Ce, Pr, and Nd are rare earth elements with strongly localized f electrons, it should be careful for their first-principles calculations. In transitional metal oxides or cerium oxides, Hubbard U correction to the standard DFT calculation works well for adjusting the band gap by taking into account of the orbital dependence of the intra-atomic Coulomb interaction.[27] In fact, the empirical Hubbard U correction is controversial for the first-principles calculations. In the recent work, Chen et al. studied the electronic and optical properties of rare-earth-doped VO2 nanoparticles,[28] they did not apply Hubbard U correction on lanthanides but on vanadium. Furthermore, Hao proved that the on-site Coulomb interaction has little effect on the description of Ce in iron solid solutions.[29] In view of this fact, we have selected Nd with most 4f electrons to examine the effect of the on-site Coulomb interaction on the segregation energy of Nd at GB in iron in GGA +U calculations. The results are listed in Table
Lanthanides, with large atomic size, could prefer to occupy a substitutional site rather than an interstitial site. We could examine the segregation behaviors by putting fission product X atom at five different substitutional sites near the GB, sites 0–4 in Fig.
As we know, we can estimate the occupation probability of the impurity near the GB using the McLean’s equation[30]
Based on the McLean’s equation, we present the occupation probability at three temperatures for various impurity concentrations in the bulk in Fig.
In order to discuss the effects of fission products La, Ce, Pr, and Nd atoms on GB cohesion, it is convenient to investigate the strengthening energy based on the thermodynamic approach of Rice and Wang.[15] Within the first-principles calculation, it can be defined as the difference between the binding energy of an impurity to the GB and that to the FS slab,
The fission products have a strong driving force to segregate to the GB with a range of 4 layers, not only for mirror plane site 0, but for sites 1, 2, and 3 in Table
The embrittlement behaviors of four lanthanide elements above can be attributed to the atomic size of Ln atoms and their magnetism characters. It has been shown that the relative embrittling or cohesion enhancing behavior of segregated impurity atoms is mainly determined by the atomic size and their bonding properties.[18] As we know, the atomic sizes of lanthanide elements gradually decrease as the atomic number increases. At first, the excess volume change caused by Ln absorbed to the GB can be generally an evaluation of atomic size. In Fig.
Using first-principles density calculations, we have investigated the segregation energy of Ln fission products (La, Ce, Pr, and Nd) near Σ3(111) tilt symmetric GB and their effects on the intergranular embrittlement in α-Fe. Firstly, we determined the segregation energies of La, Ce, Pr, and Nd at different substitutional sites near the GB. The results show that they all tend to segregate to Σ3(111)[
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