Related references
Note: Only part of the references are listed.Dual ion irradiation of commercial and advanced alloys: Evaluating microstructural resistance for high dose core internals
C. R. Lear et al.
JOURNAL OF NUCLEAR MATERIALS (2019)
A historical perspective on understanding IASCC
Peter L. Andresen et al.
JOURNAL OF NUCLEAR MATERIALS (2019)
A mechanistic study of SCC in Alloy 600 through high-resolution characterization
Zhao Shen et al.
CORROSION SCIENCE (2018)
Correlation of microstructure and stress corrosion cracking initiation behaviour of the fusion boundary region in a SA508 Cl. 3-Alloy 52M dissimilar weld joint in primary pressurized water reactor environment
Lijin Dong et al.
CORROSION SCIENCE (2018)
Grain boundary selective oxidation and intergranular stress corrosion crack growth of high-purity nickel binary alloys in high-temperature hydrogenated water
S. M. Bruemmer et al.
CORROSION SCIENCE (2018)
Microstructure and corrosion behavior of the heat affected zone of a stainless steel 308L-316L weld joint
Cheng Ma et al.
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY (2018)
Microstructure and intergranular stress corrosion cracking susceptibility of a SA508-52M-316L dissimilar metal weld joint in primary water
Lijin Dong et al.
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY (2018)
Effect of the Amount of Cold Work on Corrosion of Type 304 Nuclear Grade Stainless Steel in High-Temperature Water
Ping Deng et al.
CORROSION (2017)
Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water
Ping Deng et al.
CORROSION SCIENCE (2017)
Effects of electropolishing on corrosion and stress corrosion cracking of Alloy 182 in high temperature water
Yaolei Han et al.
CORROSION SCIENCE (2017)
Corrosion of nickel-base alloys in primary medium of pressurized water reactors: New insights on the oxide growth mechanisms and kinetic modelling
Loic Marchetti et al.
CORROSION SCIENCE (2016)
Stress corrosion cracking in the heat affected zone of a stainless steel 308L-316L weld joint in primary water
Lijin Dong et al.
CORROSION SCIENCE (2016)
Effect of electropolishing on corrosion of nuclear grade 316L stainless steel in deaerated high temperature water
Yaolei Han et al.
CORROSION SCIENCE (2016)
Correlation between locally deformed structure and oxide film properties in austenitic stainless steel irradiated with neutrons
Yasuhiro Chimi et al.
JOURNAL OF NUCLEAR MATERIALS (2016)
Quantitative analysis of localized stresses in irradiated stainless steels using high resolution electron backscatter diffraction and molecular dynamics modeling
D. C. Johnson et al.
SCRIPTA MATERIALIA (2016)
Effect of dissolved hydrogen on corrosion of 316NG stainless steel in high temperature water
Lijin Dong et al.
NUCLEAR ENGINEERING AND DESIGN (2015)
Strain localization at dislocation channel-grain boundary intersections in irradiated stainless steel
M. D. McMurtrey et al.
INTERNATIONAL JOURNAL OF PLASTICITY (2014)
Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water
Kale J. Stephenson et al.
JOURNAL OF NUCLEAR MATERIALS (2014)
Aspects of ion irradiations to study localized deformation in austenitic stainless steels
Zhijie Jiao et al.
JOURNAL OF NUCLEAR MATERIALS (2014)
Local strain distribution near grain boundaries under tensile stresses in highly irradiated SUS316 stainless steel
Koji Fukuya et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
Influence of Irradiation on the Oxide Film Formed on 316 L Stainless Steel in PWR Primary Water
Stephane Perrin et al.
OXIDATION OF METALS (2013)
The role of cold work and applied stress on surface oxidation of 304 stainless steel
Sergio Lozano-Perez et al.
CORROSION SCIENCE (2012)
Environmentally assisted crack growth in one-dimensionally cold worked Alloy 690TT in primary water
Q. J. Peng et al.
CORROSION SCIENCE (2012)
Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water
Sarata Cisse et al.
CORROSION SCIENCE (2012)
Nanoscale characterisation of grain boundary oxidation in cold-worked stainless steels
Karen Kruska et al.
CORROSION SCIENCE (2012)
IASCC Initiation in Highly Irradiated Stainless Steels under Uniaxial Constant Load Conditions
Hiromasa NISHIOKA et al.
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY (2012)
Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water—Effect of Chromium Content in Alloys and Dissolved Hydrogen—
Takumi TERACHI et al.
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY (2012)
Assessment of local deformation using EBSD: Quantification of local damage at grain boundaries
Masayuki Kamaya
MATERIALS CHARACTERIZATION (2012)
Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels
Z. Jiao et al.
ACTA MATERIALIA (2011)
Effects of cold working path on strain concentration, grain boundary microstructure and stress corrosion cracking in Alloy 600
J. Hou et al.
CORROSION SCIENCE (2011)
Sensitivity of stress corrosion cracking of stainless steel to surface machining and grinding procedure
A. Turnbull et al.
CORROSION SCIENCE (2011)
Effects of cold working degrees on grain boundary characters and strain concentration at grain boundaries in Alloy 600
J. Hou et al.
CORROSION SCIENCE (2011)
Impact of localized deformation on IASCC in austenitic stainless steels
Z. Jiao et al.
JOURNAL OF NUCLEAR MATERIALS (2011)
An EBSD examination of SUS316 stainless steel irradiated to 73 dpa and deformed at 593 K
Koji Fukuyaa et al.
JOURNAL OF NUCLEAR MATERIALS (2011)
Influence of crystal orientation on hardness and nanoindentation deformation in ion-irradiated stainless steels
Terumitsu Miura et al.
JOURNAL OF NUCLEAR MATERIALS (2011)
The role of irradiated microstructure in the localized deformation of austenitic stainless steels
Z. Jiao et al.
JOURNAL OF NUCLEAR MATERIALS (2010)
Atom-probe tomography characterization of the oxidation of stainless steel
Sergio Lozano-Perez et al.
SCRIPTA MATERIALIA (2010)
Early stage SCC initiation analysis of fcc Fe-Cr-Ni ternary alloy at 288 °C: A quantum chemical molecular dynamics approach
Nishith Kumar Das et al.
CORROSION SCIENCE (2009)
Characterization of deformation structure in ion-irradiated stainless steels
Terumitsu Miura et al.
JOURNAL OF NUCLEAR MATERIALS (2009)
Localized deformation and IASCC initiation in austenitic stainless steels
Z. Jiao et al.
JOURNAL OF NUCLEAR MATERIALS (2008)
Strain hardening and long-range internal stress in the localized deformation of irradiated polycrystalline metals
Thak Sang Byun et al.
JOURNAL OF NUCLEAR MATERIALS (2006)
Microstructural evolution of proton irradiated T91
G. Gupta et al.
JOURNAL OF NUCLEAR MATERIALS (2006)
Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600
J Panter et al.
JOURNAL OF NUCLEAR MATERIALS (2006)
An ATEM study of oxidation behavior of SCC crack tips in 304L stainless steel in high temperature oxygenated water
YH Lu et al.
JOURNAL OF NUCLEAR MATERIALS (2005)
Dislocation-obstacle interactions: Dynamic experiments to continuum modeling
IM Robertson et al.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING (2005)
Share Paper
