Environmental degradation of structural materials in liquid lead-and lead-bismuth eutectic-cooled reactors

X Gong, MP Short, T Auger… - Progress in materials …, 2022 - Elsevier
Liquid lead (Pb)-and lead–bismuth eutectic (LBE)-cooled fast neutron reactors (Gen-IV
LFRs) are one of the most technologically mature fission reactor technologies, due to their …

Sintering of MAX-phase materials by spark plasma and other methods

J Lyu, EB Kashkarov, N Travitzky, MS Syrtanov… - Journal of Materials …, 2021 - Springer
This review focuses on the comparison of the spark plasma sintering (SPS) with other
fabrication methods of MAX-phase materials. In the view of optimizing properties for …

Phase transformation and amorphization resistance in high-entropy MAX phase M2SnC (M= Ti, V, Nb, Zr, Hf) under in-situ ion irradiation

S Zhao, L Chen, H Xiao, J Huang, Y Li, Y Qian… - Acta Materialia, 2022 - Elsevier
Chemical complexity significantly affects structures and properties in materials, such as high-
entropy alloys and oxides. In this study, we firstly studied the radiation effects in high-entropy …

Point defect properties in high entropy MAX phases from first-principles calculations

H Xiao, S Zhao, Q Liu, Y Li, S Zhao, F Luo, Y Wang… - Acta Materialia, 2023 - Elsevier
MAX phase materials exhibit both metal and ceramic properties due to their unique
laminated atomic structures, making them promising candidates in advanced nuclear energy …

Ti3AlC2, a candidate structural material for innovative nuclear energy system: The microstructure phase transformation and defect evolution induced by energetic …

T Deng, J Sun, P Tai, Y Wang, L Zhang, H Chang… - Acta Materialia, 2020 - Elsevier
For the structure materials applied in the innovative nuclear energy system, the strongly
environment radiation source is always a big concern which will severely degrade the …

Early stages of dissolution corrosion in 316L and DIN 1.4970 austenitic stainless steels with and without anticorrosion coatings in static liquid lead-bismuth eutectic …

E Charalampopoulou, K Lambrinou… - Materials …, 2021 - Elsevier
This work addresses the early stages (≤ 1000 h) of the dissolution corrosion behavior of
316L and DIN 1.4970 austenitic stainless steels in contact with oxygen-poor (CO< 10− 8 …

High-temperature oxidation behavior of HiPIMS as-deposited Cr–Al–C and annealed Cr2AlC coatings on Zr-based alloy

M Ougier, A Michau, F Lomello, F Schuster… - Journal of Nuclear …, 2020 - Elsevier
Protective coatings of Zr-based claddings have been proposed for the development of
Accident Tolerant nuclear Fuel (ATF). Coatings forming stable oxides at high temperature …

Study of the Effect of Nanostructured Grains on the Radiation Resistance of Zirconium Dioxide Ceramics During Gas Swelling under High-dose Irradiation with Helium …

AL Kozlovskiy, M Konuhova, DI Shlimas… - ES Materials & …, 2024 - espublisher.com
The paper is devoted to the study of the influence of variation of zirconium dioxide (ZrO 2)
ceramics grain sizes on the resistance to radiation-induced swelling under irradiation with …

[HTML][HTML] Optical response, lithiation and charge transfer in Sn-based 211 MAX phases with electron localization function

MA Hadi, N Kelaidis, PP Filippatos… - journal of materials …, 2022 - Elsevier
In this study, optical response, lithiation and charge transfer in existing M 2 SnC MAX
phases with electron localization function (ELF) were investigated for the first time using the …

[HTML][HTML] Radiation effects in Mn+ 1AXn phases

C Wang, CL Tracy, RC Ewing - Applied Physics Reviews, 2020 - pubs.aip.org
M n+ 1 AX n phases exhibit unique laminated atomic structures that result in properties
typical of both ceramics and metals. Due to their unusual characteristics, these materials …