Irradiation-induced swelling of pure chromium with 5 MeV Fe ions in the temperature range 450–650 °C

Ryabikovskaya, Ekaterina; French, Aaron; Gabriel, Adam; Kim, Hyosim; Wang, Tianyao; Shirvan, Koroush; Garner, F.А.; Shao, Lin

doi:10.1016/j.jnucmat.2020.152585

Cited by 13 publications

(6 citation statements)

References 34 publications

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“…The irradiation condition (dose and temperature) and superlattice properties (void diameter r d , lattice parameter a L , and structure) for the VSL in bcc W under neutron irradiation (Amino et al, 2016) are all within the ranges reported before (Ghoniem et al, 2001). The planar ordering of voids in Cr under 5 MeV Fe + irradiation (Ryabikovskaya et al, 2021) is probably an early stage of superlattice formation. Samples irradiated in the same conditions were re-characterized by Sun et al (Sun et al, 2022), and bodycentered-tetragonal (bct) VSLs were identified, indicating that the VSLs were coherent but not isomorphic with the matrix.…”

Section: Void Superlattice-vslsupporting

confidence: 63%

A review of void and gas bubble superlattices self-organization under irradiation

Zhang

2023

Front. Nucl. Eng.

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Irradiation by high-energy particles has been well known as a destructive force that “damages” crystalline materials by creating lattice defects. One surprising outcome from irradiation is the self-organization of void superlattices and gas bubble superlattices in various materials under irradiation. While these superlattices exhibit crystal structures that mimic atomic lattices, their self-organization takes place in far-from-equilibrium environment. A thermodynamic driving force that entails ordering is either absent or yet to be identified. In the past few decades, extensive research efforts have been made to generate such superlattices and to discern their formation mechanisms. While a consensus is yet to reach, these studies have substantially enriched our understanding on defect evolution and self-organization under irradiation. Appending previous reviews that are mostly done two decades ago, this article presents a comprehensive review of new experimental, theoretical, and simulational studies of void and gas bubble superlattices in the past two decades. An in-depth discussion on the formation mechanisms and their implications on superlattice properties is provided for the purpose of encouraging future studies.

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Section: Void Superlattice-vslsupporting

confidence: 63%

A review of void and gas bubble superlattices self-organization under irradiation

Zhang

2023

Front. Nucl. Eng.

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“…The swelling of SiC by neutrons saturated at less than 1 dpa and showed relatively good agreement to the swelling by Si Although the number of displacements per atom in the surface irradiated by ions had a depth distribution as shown in Figure 2c, the swelling at 3 dpa was almost the same over the damage region because swelling saturation occurred at less than 1 dpa. Microstructures and swelling of pure Ti, pure Cr, and Cr coating irradiated at temperatures from 423 K to 723 K are summarized in Table 3 [43,[70][71][72][73][74][75]. The microstructural features of pure Ti irradiated with neutrons and ions are generically classified as black spots or dislocation loops at these temperatures.…”

Section: Swellingmentioning

confidence: 99%

“…Few results have been reported about swelling of pure Ti. Voids of 1.5-4 nm in diameter were observed in the microstructure of pure Cr irradiated with neutrons and ions at temperatures between 593 K and 723 K [43,74,75]. The swellings were estimated from size and density of voids.…”

Section: Swellingmentioning

confidence: 99%

Radiation Effect in Ti-Cr Multilayer-Coated Silicon Carbide under Silicon Ion Irradiation up to 3 dpa

et al. 2022

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Replacement of conventional Zircaloy fuel cladding with silicon carbide (SiC) fuel cladding is expected to significantly decrease the amount of hydrogen generated from fuel claddings by the reaction with steam during severe accidents. One of their critical issues addressed regarding practical application has been hydrothermal corrosion. Thus, the corrosion resistant coating technology using a Ti-Cr multilayer was developed to suppress silica dissolution from SiC fuel cladding into reactor coolant under normal operation. The effect of radiation on adhesion of the coating to SiC substrate and its microstructure characteristics were investigated following Si ion irradiation at 573 K up to 3 dpa for SiC. Measurement of swelling in pure Ti, pure Cr and SiC revealed that the maximum inner stress attributed to the swelling difference was generated between the coating and SiC substrate by irradiation of 1 dpa. No delamination and cracking were observed in cross-sectional specimens of the coated SiC irradiated up to 3 dpa. According to analyses using transmission electron microscopy, large void formation and cascade mixing due to irradiation were not observed in the coating. The swelling in the coating at 573 K was presumed to be caused by another mechanism during radiation such as point defects rather than void formation.

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“…Currently, coating candidates include FeCrAl [3], Cr [4], and Al-containing MAX (M n + 1 AX n , M = early transition metal, A = group-A element, X = C or N, n = 1-3) phase [5]. However, the easy swelling of Cr at relatively low damage levels [6], each amorphization of MAX phase alloys (Ti 2 AlC as one example) at interfaces [7], and complicated interaction reactions between FeCrAl and Zircaloy require further investigation and optimization [8]. Hence, other coating alternatives are still required.…”

Section: Introductionmentioning

confidence: 99%

ZrN Phase Formation, Hardening and Nitrogen Diffusion Kinetics in Plasma Nitrided Zircaloy-4

et al. 2021

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Plasma nitridation was conducted to modify the surfaces of Zircaloy-4. Scanning electron microscopy (SEM), transmission electron microscopy (TEM), and Raman analysis were used to characterize microstructures and phases. Surface indentation and cross-sectional indentation were performed to evaluate mechanical property changes. Nitridation forms a thin layer of ZrN phase, followed by a much deeper layer affected by nitrogen diffusion. The ZrN phase is confirmed by both TEM and Raman characterization. The Raman peaks of ZrN phase show a temperature dependence. The intensity increases with increasing nitridation temperatures, reaches a maximum at 700 °C, and then decreases at higher temperatures. The ZrN layer appears as continuous small columnar grains. The surface polycrystalline ZrN phase is harder than the bulk by a factor of ~8, and the nitrogen diffusion layer is harder by a factor of ~2–5. The activation energy of nitrogen diffusion was measured to be 2.88 eV. The thickness of the nitrogen-hardened layer is controllable by changing the nitridation temperature and duration.

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Irradiation-induced swelling of pure chromium with 5 MeV Fe ions in the temperature range 450–650 °C

Cited by 13 publications

References 34 publications

A review of void and gas bubble superlattices self-organization under irradiation

A review of void and gas bubble superlattices self-organization under irradiation

Radiation Effect in Ti-Cr Multilayer-Coated Silicon Carbide under Silicon Ion Irradiation up to 3 dpa

ZrN Phase Formation, Hardening and Nitrogen Diffusion Kinetics in Plasma Nitrided Zircaloy-4

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