Diffusion bonding and transient liquid phase (TLP) bonding of type 304 and 316 austenitic stainless steel—A review of similar and dissimilar material joints

A AlHazaa, N Haneklaus - Metals, 2020 - mdpi.com
Similar and dissimilar material joints of AISI grade 304 (1.4301) and AISI grade 316 (1.4401)
austenitic stainless steel by solid state diffusion bonding and transient liquid phase (TLP) …

Plasma electrolytic oxidation ceramic coatings on zirconium (Zr) and zralloys: Part i—Growth mechanisms, microstructure, and chemical composition

N Attarzadeh, CV Ramana - Coatings, 2021 - mdpi.com
Recently, a significant number of research projects have been directed towards designing
and developing ceramic coatings for zirconium-based substrates due to their outstanding …

Machine learning for metallurgy V: A neural-network potential for zirconium

M Liyanage, D Reith, V Eyert, WA Curtin - Physical Review Materials, 2022 - APS
The mechanical performance—including deformation, fracture and radiation damage—of
zirconium is determined at the atomic scale. With Zr and its alloys extensively used in the …

High-intensity low energy titanium ion implantation into zirconium alloy

AI Ryabchikov, EB Kashkarov, NS Pushilina… - Applied Surface …, 2018 - Elsevier
This research describes the possibility of ultra-high dose deep titanium ion implantation for
surface modification of zirconium alloy Zr-1Nb. The developed method based on repetitively …

Microstructure and shear strength of SiC/Zr joint brazed with LiAlSiO4/graphene-coated Cu-foam composite interlayer

Z Luo, G Wang, Y Zhao, C Tan, R He - Ceramics International, 2023 - Elsevier
In the present work, the microstructures and mechanical properties of Cu-foam-(graphene,
LiAlSiO 4 and graphene/LiAlSiO 4) and a CoCrNiFeCuSn high-entropy alloy as a composite …

[PDF][PDF] Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes

D Kamerman, F Cappia, K Wheeler, P Petersen… - Nuclear Materials and …, 2022 - Elsevier
Zirconium alloys have long been used in the commercial nuclear power industry as the fuel
rod cladding material of choice due to their neutron transparency, excellent mechanical …

[HTML][HTML] Co-deformation and dynamic annealing effects on the texture development during alpha–beta processing of a model Zr-Nb alloy

CS Daniel, A Garner, PD Honniball, L Bradley… - Acta Materialia, 2021 - Elsevier
The in-service properties and performance of dual-phase Zr and Ti alloys depend on their
crystallographic texture, which develops during hot-working and is affected by interactions …

[HTML][HTML] On mechanical response of Zircaloy-4 under a wider range of stress states: From uniaxial tension to uniaxial compression

M Paredes, T Wierzbicki - International Journal of Solids and Structures, 2020 - Elsevier
The present work summarizes the experimental campaign and computational effort
performed on Zircaloy-4 material commonly used in nuclear applications. The Zircaloy-4 …

Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes

D Kamerman, M Nelson - Nuclear Technology, 2023 - Taylor & Francis
The following work is motivated by the desire to devise an internal pressure test that can
mimic a displacement-controlled loading scenario and demonstrate how to apply the …

[HTML][HTML] A detailed study of texture changes during alpha–beta processing of a zirconium alloy

CS Daniel, PD Honniball, L Bradley, M Preuss… - Journal of Alloys and …, 2019 - Elsevier
The properties and performance of Zr-2.5 Nb alloys are strongly influenced by their
crystallographic texture. As in similar Ti alloys, the texture evolution during hot-processing …