Effect of hydride orientation on tensile properties and crack formation in zirconium alloy cladding tubes

X Hong, F Ma, J Zhang, D Du, H Tian, Q Xu… - Journal of Nuclear …, 2024‏ - Elsevier
Hydride precipitation and reorientation are of great importance to evaluate considering their
detrimental influence on mechanical properties of nuclear fuel claddings. In this work, a fully …

Recrystallization and grain growth of Zr-Nb-Sn alloy in 400–500° C and effect on hydride embrittlement

S Kim, D Son, JH Kang, Y Lee - Journal of Nuclear Materials, 2023‏ - Elsevier
The recrystallization and grain growth of a reactor-grade Zr-Nb-Sn alloy were experimentally
investigated in the temperature range of 400–500° C. Electron backscatter diffraction …

Fractal pattern of δ-hydride with stress-state

A Das - Chaos, Solitons & Fractals, 2024‏ - Elsevier
Fractal dimension of any defect in microstructure is a critical parameter for their geometric
irregularities, pattern of arrangements and morphological attributes. The fractal dimensions …

Relations of microstructural attributes and strength-ductility of zirconium alloys with hydrides

C Fang, X Guo, J Li, G Chen - Chinese Journal of Mechanical Engineering, 2023‏ - Springer
As the first safety barrier of nuclear reactors, zirconium alloy cladding tubes have attracted
extensive attention because of its good mechanical properties. The strength and ductility of …

Hydride orientation near pressure tube-end fitting rolled joints

TN Murty, RK Sharma, GSR Krishna, S Ghosh… - International Journal of …, 2024‏ - Elsevier
Abstract The connection between Zr–2.5% Nb pressure tubes and modified martensitic
stainless steel-403 end fittings in Pressurized Heavy Water Reactors (PHWRs) at the rolled …

[HTML][HTML] Corrosion of Chromium Coating Fabricated on Zircaloy-4 Substrate

F Golgovici, D Diniași, PP Dincă, B Butoi, I Demetrescu - Materials, 2024‏ - mdpi.com
In the nuclear industry, coated cladding is a topical problem and it is chosen as the near-
term and most promising ATF (Accident-Tolerant Fuel) cladding concept. The main objective …

Evolution of an approach to the modeling of zirconium hydrides morphology based on Monte-Carlo method in 3D representation

TN Aliev, MY Kolesnik - Letters on Materials, 2023‏ - lettersonmaterials.com
Simulation of hydrides' morphology in zirconium in 3D representation assuming classical
heterogenous nucleation and diffusion growth with taking into account the mutual influence …

Characterization of Hydride Precipitation and Reorientation in Zircaloy-4 at Different Metallurgical States

M Maric, R Thomas, T Ungár, G Zilahi, C Hunt… - 2023‏ - asmedigitalcollection.asme.org
Hydride precipitation and reorientation have the potential to embrittle zirconium alloys. This
study aims to better understand the influence of the zirconium microstructure on hydride …

[PDF][PDF] Modelling the morphology of hydrides in fuel rod cladding under the conditions of the long-term bundle test in the framework of the SPIZWURZ project

M Kolesnik, J Stuckert, M Grosse - Proceedings of TopFuel 2024 …, 2024‏ - researchgate.net
Modelling the morphology of hydrides in fuel rod cladding under the conditions of the long-term
bundle test in the framework of Page 1 Modelling the morphology of hydrides in fuel rod …

[PDF][PDF] Study of hydride interconnectivity of reactor-grade Zircaloy nuclear fuel cladding with EBSD characterization

김상범 - 2023‏ - s-space.snu.ac.kr
Among various degradation mechanisms affecting nuclear fuel cladding, hydrogen-induced
embrittlement is known to be major degradation factor. For decades, extensive studies have …