The amorphous AlCrFeMoTi high-entropy alloy (HEA) coating with near-equal molar ratio
was successfully deposited on F/M substrate by magnetron co-sputtering technique and …

TiAlN coating are used as nuclear reactor cladding protective materials due to their good
corrosion resistance. However, long-term exposure to an extremely harsh nuclear …

This study presents a Monte‐Carlo simulation‐based approach to investigate how stochastic
crane movements affect the structural reliability of the rail beam considering radiation effects …

In this paper, tensile test and creep‐fatigue test at 650° C were carried out for 316L steel
with and without prior thermal aging. The effect of aging on creep‐fatigue interaction of 316L …

In the thermal–mechanical couplin-g field caused by pressurized thermal shock (PTS), crack
propagation in nuclear reactor pressure vessel (RPV) is easy to occur in the base wall …

The creep deformation behavior and age strengthening behavior of 304 stainless steel
under high stress levels were systematically studied by uniaxial creep test, tensile test, XRD …

Cast steel joints are widely used in engineering structures and exhibit different mechanical
responses in service environments at elevated temperatures. Hence, the temperature …

Creep crack growth is a life-limiting failure mechanism in high-temperature metallic
components. The creep crack growth response is linked to the underlying creep deformation …

In order to reveal the effect of irradiation damage caused by high-level liquid radioactive
wastes on the welded joint of the container, the irradiation-induced microstructure evolution …

This study presents a comparison between computational simulations and experimental
tests of fatigue crack growth (FCG) in austenitic stainless-steel Fe-25Ni-20Cr (Alloy 709) at …