Zr–Nb alloy is successfully used as structural materials in nuclear reactors. However, its
widespread application is restricted by corrosion due to complex in-pile environments. This …

Ion irradiation offers a promising strategy to emulate the irradiation damage induced by
energetic neutrons. However, the characterization of the mechanical properties of ion …

In this work, the radiation responses of Zr/Nb nanostructured metallic multilayers (NMMs) are
studied. The nanostructures with different layer thicknesses were deposited on Si (1 1 1) …

In this work, an integrated approach including experimental examinations and theoretical
modeling was employed to examine the temperature-dependent hardening of structural …

An investigation into the effects of proton beam exposure on high-and low-copper structural
materials for nuclear reactors has been carried out. The aim of this work was to investigate …

This review summarizes the development of the Gas-Cooled Fast Reactor (GFR) concept
from the early 1970s until now, focusing specifically on structural materials and advanced …

This study aimed to investigate the microstructure information and mechanical behavior of
ion-irradiated zirconium (Zr) alloys through a combination of experimental measurements …

Zirconium based alloys are viewed as one of the most important fuel cladding materials, and
alloy elements play a crucial role in improving its irradiation resistance, especially Nb and …

The microstructure and texture evolution of Zr-xNb-0.4 Mo (x= 0, 0.2, 0.4, 0.6 and 1.0 wt%)
alloys are characterized using scanning electron microscopy (SEM), transmission electron …

In this work, the microstructure and subsurface hardness of pure Zr and Zr-xFe (x= 0.2, 0.4,
0.6) model alloys were investigated at elevated temperatures (298–573 K) by means of …