Materials for future nuclear energy systems
Materials for future nuclear energy systems must operate under more extreme conditions
than those in current Gen II or Gen III systems. These conditions include higher temperature …
than those in current Gen II or Gen III systems. These conditions include higher temperature …
Progress in corrosion resistant materials for supercritical water reactors
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 …
cooled reactors that operate above the thermodynamic critical point of water (374° C, 22.1 …
Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation
In recent years, high entropy alloys (HEAs) have attracted significant attention due to their
excellent mechanical properties and good corrosion resistance, making them potential …
excellent mechanical properties and good corrosion resistance, making them potential …
Irradiation damage in (Zr0. 25Ta0. 25Nb0. 25Ti0. 25) C high-entropy carbide ceramics
This research revealed the mechanisms of irradiation damage in the novel high entropy
ceramic materials.(Zr 0.25 Ta 0.25 Nb 0.25 Ti 0.25) C high-entropy carbide ceramics …
ceramic materials.(Zr 0.25 Ta 0.25 Nb 0.25 Ti 0.25) C high-entropy carbide ceramics …
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
Application of advanced oxidation-resistant iron alloys as light water reactor fuel cladding is
proposed. The motivations are based on specific limitations associated with zirconium …
proposed. The motivations are based on specific limitations associated with zirconium …
Probing grain boundary sink strength at the nanoscale: Energetics and length scales of vacancy and interstitial absorption by grain boundaries in -Fe
The energetics and length scales associated with the interaction between point defects
(vacancies and self-interstitial atoms) and grain boundaries in bcc Fe was explored …
(vacancies and self-interstitial atoms) and grain boundaries in bcc Fe was explored …
[PDF][PDF] 1.03-Radiation-Induced effects on microstructure
SJ Zinkle - Comprehensive nuclear materials, 2012 - researchgate.net
Irradiation of materials with particles that are sufficiently energetic to create atomic
displacements can induce significant microstructural alteration, ranging from crystalline-to …
displacements can induce significant microstructural alteration, ranging from crystalline-to …
Emulation of neutron irradiation effects with protons: validation of principle
This paper presents the results of the irradiation, characterization and irradiation assisted
stress corrosion cracking (IASCC) behavior of proton-and neutron-irradiated samples of …
stress corrosion cracking (IASCC) behavior of proton-and neutron-irradiated samples of …
Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels
The irradiation-induced microstructure and irradiation-assisted stress corrosion cracking
(IASCC) behavior of additively manufactured (AM) 316L stainless steels produced by laser …
(IASCC) behavior of additively manufactured (AM) 316L stainless steels produced by laser …
Current understanding of radiation-induced degradation in light water reactor structural materials
K Fukuya - Journal of Nuclear Science and Technology, 2013 - Taylor & Francis
Current phenomenological knowledge and understanding of mechanisms are reviewed for
radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted …
radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted …