The aim of the present article is to review some of the common corrosion phenomena and
describe the predominant corrosion mechanisms in high-temperature and supercritical …

Current understanding of radiation-induced material changes that occur in light-water-
reactor (LWR) core components is critically reviewed and linked to intergranular failure …

Nondestructive three-dimensional map** of grain shape, crystallographic orientation, and
grain boundary geometry by diffraction contrast tomography (DCT) provides opportunities for …

Irradiation of materials with particles that are sufficiently energetic to create atomic
displacements can induce significant microstructural alteration, ranging from crystalline-to …

Tempering of 13 wt.% Cr martensitic stainless steel resulted in nano-sized M 3 C carbides at
300° C, nano-sized Cr-rich M 23 C 6 carbides at 550° C and sub-micron sized Cr-rich M 23 …

Additively manufactured (AM) 316 L stainless steel (SS) after hot isostatic pressing (HIP)
was found to exhibit superior resistance to irradiation-assisted stress corrosion cracking …

Supercritical water reactors (SCWRs) are a kind of high-temperature, high-pressure water-
cooled reactors that operate above the thermodynamic critical point of water (374° C, 22.1 …

Radiation-induced segregation is well known in metals, but has been rarely studied in
ceramics. We discover that radiation can induce notable segregation of one of the …

The stress corrosion cracking (SCC) propagation behavior of 20% cold worked 316 L
stainless steel (SS) and Alloy 690 was investigated in high-temperature oxygenated water …

Cold work of materials, dissolved oxygen and chloride in water are crucial factors that
accelerate the stress corrosion cracking (SCC) crack growth rate of stainless steel in high …