2020
DOI: 10.1016/j.commatsci.2020.109775
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Phase-field modeling of hydride reorientation in zirconium cladding materials under applied stress

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Cited by 14 publications
(5 citation statements)
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“…The average growth rate of the hydride has an opposite trend to the elastic interaction energy in both vertical and horizontal directions, which is consistent with the effect of the elastic interaction energy on the interface moving velocity in Eq. (38). From Fig.…”
Section: Effect Of the Loss Of Interfacial Coherencymentioning
confidence: 97%
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“…The average growth rate of the hydride has an opposite trend to the elastic interaction energy in both vertical and horizontal directions, which is consistent with the effect of the elastic interaction energy on the interface moving velocity in Eq. (38). From Fig.…”
Section: Effect Of the Loss Of Interfacial Coherencymentioning
confidence: 97%
“…Heo et al [11] developed a polycrystalline PF model considering the loss of the interfacial coherency and the grain boundary segregation to investigate δ -hydride growth behavior. Additionally, Lin et al [37] and Shin et al [38] examined the reorientation behavior of δ -hydrides under applied stress fields. Simon et al [39] developed a quantitative PF model for δ -hydrides and analyzed the role of anisotropic elastic interaction on hydride stacking and reorientation.…”
Section: Introductionmentioning
confidence: 99%
“…The phase-field method has been widely used to simulate the microstructure of hydride in zirconium alloy [25][26][27][28][29]. Usually, the majority of research on stress-induced (internal stress and external load) nucleation, growth, stacking, and reorientation behavior of δ hydrides [30][31][32][33]. However, these theoretical achievements were based on a coherent interface between the precipitate phase and the matrix phase.…”
Section: Introductionmentioning
confidence: 99%
“…Zirconium (Zr) is a key material in nuclear engineering because of its small neutron absorption cross-section and excellent oxidation resistance [1][2][3]. The main risk of Zr-based materials in the nuclear system is hydride-induced degradation, such as hydride precipitation [4], hydride reorientation [5][6][7] and delayed hydride cracking [8]. Therefore, it is extremely important to understand the interaction between Zr species and their hydrides to ensure the safety of nuclear systems.…”
Section: Introductionmentioning
confidence: 99%
“…The original theory describes the interaction between a spherical particle and an isotropic grain boundary [9]. For the case of δ zirconium hydride, which is platelet-shaped [5,10], we need to understand the interaction between a grain boundary with highly anisotropically shaped particles. The interaction between a grain boundary and ellipsoidal particles was estimated by an analytic method [11] and numerical simulations [12,13].…”
Section: Introductionmentioning
confidence: 99%