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-induced solute segregation in metallic alloys

AJ Ardell, P Bellon - Current Opinion in Solid State and Materials Science, 2016‏ - Elsevier
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 …

Dislocation channel broadening–A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless …

J Yang, L Hawkins, Z Shang, EA McDermott, BK Tsai… - Acta Materialia, 2024‏ - Elsevier
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 …

Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels

Z Jiao, GS Was - Acta Materialia, 2011‏ - Elsevier
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 …

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 …

Evolution of cellular dislocation structures and defects in additively manufactured austenitic stainless steel under ion irradiation

S Li, J Hu, WY Chen, J Yu, M Li, Y Wang - Scripta Materialia, 2020‏ - Elsevier
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 …

Tailoring plasticity of austenitic stainless steels for nuclear applications: Review of mechanisms controlling plasticity of austenitic steels below 400 C

GM de Bellefon, JC Van Duysen - Journal of Nuclear Materials, 2016‏ - Elsevier
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 …

Atomic scale investigation of radiation-induced segregation in austenitic stainless steels

A Etienne, B Radiguet, NJ Cunningham… - Journal of Nuclear …, 2010‏ - Elsevier
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 …

Quantitative atom probe tomography characterization of microstructures in a proton irradiated 304 stainless steel

Y Chen, PH Chou, EA Marquis - Journal of Nuclear Materials, 2014‏ - Elsevier
Irradiation of 304 stainless steels induces complex microstructural changes such as solute
clustering, precipitation, and segregation to dislocations, which have been best …

Comparison of radiation-induced segregation in ultrafine-grained and conventional 316 austenitic stainless steels

A Etienne, B Radiguet, NJ Cunningham, GR Odette… - Ultramicroscopy, 2011‏ - Elsevier
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 …