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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 …
Radiation-induced solute segregation in metallic alloys
The subject of radiation-induced solute segregation (RIS) in metallic alloys is reviewed. RIS
manifests itself in several different ways, including diffusion to point-defect sinks …
manifests itself in several different ways, including diffusion to point-defect sinks …
Dislocation channel broadening–A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless …
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 …
was found to exhibit superior resistance to irradiation-assisted stress corrosion cracking …
Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels
Three stainless steel alloys, high-purity 304 (HP304), high-purity 304 with high Si (HP304+
Si) and commercial purity 304 (CP304), were irradiated with 2MeV protons to a dose of 5dpa …
Si) and commercial purity 304 (CP304), were irradiated with 2MeV protons to a dose of 5dpa …
Radiation-induced degradation of stainless steel light water reactor internals
EA Kenik, JT Busby - Materials Science and Engineering: R: Reports, 2012 - Elsevier
In order to provide a scientific basis for proposed life extension of current light water
reactors, the radiation-induced degradation of stainless steel reactor internals will be …
reactors, the radiation-induced degradation of stainless steel reactor internals will be …
Evolution of cellular dislocation structures and defects in additively manufactured austenitic stainless steel under ion irradiation
The evolution of irradiation-induced defects in additively manufactured (AM) austenitic
stainless steel was investigated in situ by 1 MeV Kr ion irradiation at 450 and 600° C in a …
stainless steel was investigated in situ by 1 MeV Kr ion irradiation at 450 and 600° C in a …
Tailoring plasticity of austenitic stainless steels for nuclear applications: Review of mechanisms controlling plasticity of austenitic steels below 400 C
AISI 304 and 316 austenitic stainless steels were invented in the early 1900s and are still
trusted by materials and mechanical engineers in numerous sectors because of their good …
trusted by materials and mechanical engineers in numerous sectors because of their good …
Atomic scale investigation of radiation-induced segregation in austenitic stainless steels
Radiation-induced precipitation and segregation in a cold-worked 316 austenitic stainless
steel irradiated with 10MeV Fe5+ ions were characterized by atom probe tomography. Ni …
steel irradiated with 10MeV Fe5+ ions were characterized by atom probe tomography. Ni …
Quantitative atom probe tomography characterization of microstructures in a proton irradiated 304 stainless steel
Irradiation of 304 stainless steels induces complex microstructural changes such as solute
clustering, precipitation, and segregation to dislocations, which have been best …
clustering, precipitation, and segregation to dislocations, which have been best …
Comparison of radiation-induced segregation in ultrafine-grained and conventional 316 austenitic stainless steels
Due to a high number density of grain boundaries acting as point defect sinks, ultrafine-
grained materials are expected to be more resistant to irradiation damage. In this context …
grained materials are expected to be more resistant to irradiation damage. In this context …