Related references
Note: Only part of the references are listed.Effect of grain boundary planes on radiation-induced segregation (RIS) at near Σ3 grain boundaries in Fe-Cr alloy under ion irradiation
Q. Barres et al.
MATERIALS CHARACTERIZATION (2022)
Investigation of deformation mechanisms in an advanced FeCrAl alloy using in-situ SEM-EBSD testing
Nitish Bibhanshu et al.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING (2022)
Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures
Keyou S. Mao et al.
ACTA MATERIALIA (2022)
A data science approach for analysis and reconstruction of spinodal-like composition fields in irradiated FeCrAl alloys
Yash Pachaury et al.
ACTA MATERIALIA (2022)
Segregation behavior and phase instability of Eurofer97 after neutron irradiation to 72 dpa
Kun Wang et al.
JOURNAL OF NUCLEAR MATERIALS (2021)
Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation
Caleb P. Massey et al.
JOURNAL OF NUCLEAR MATERIALS (2021)
Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water
Peng Wang et al.
JOURNAL OF NUCLEAR MATERIALS (2020)
Resistance of Ferritic FeCrAl Alloys to Stress Corrosion Cracking for Light Water Reactor Fuel Cladding Applications
Raul Rebak et al.
CORROSION (2020)
Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determination
Kevin G. Field et al.
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS (2019)
Diffusion of point defects in ordered and disordered Ni-Fe alloys
Shijun Zhao et al.
JOURNAL OF ALLOYS AND COMPOUNDS (2019)
Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy
Dalong Zhang et al.
JOURNAL OF NUCLEAR MATERIALS (2019)
Role of refractory inclusions in the radiation-induced microstructure of APMT
Dalong Zhang et al.
JOURNAL OF NUCLEAR MATERIALS (2018)
TEM characterization of irradiated microstructure of Fe-9%Cr ODS and ferritic-martensitic alloys
M. J. Swenson et al.
JOURNAL OF NUCLEAR MATERIALS (2018)
Impact of neutron irradiation on mechanical performance of FeCrAl alloy laser-beam weldments
M. N. Gussev et al.
JOURNAL OF NUCLEAR MATERIALS (2018)
Precipitation of α′ in neutron irradiated commercial FeCrAl alloys
Kevin G. Field et al.
SCRIPTA MATERIALIA (2018)
Oxidation behavior of high-strength FeCrAl alloys in a high-temperature supercritical carbon dioxide environment
Hongsheng Chen et al.
PROGRESS IN NATURAL SCIENCE-MATERIALS INTERNATIONAL (2018)
Utilizing FeCrAl Oxidation Resistance Properties in Water, Air and Steam for Accident Tolerant Fuel Cladding.
V. K. Gupta et al.
HIGH TEMPERATURE CORROSION AND MATERIALS CHEMISTRY 13 (2018)
Cr-induced fast vacancy cluster formation and high Ni diffusion in concentrated Ni-Fe-Cr alloys
Debajit Chakraborty et al.
JOURNAL OF ALLOYS AND COMPOUNDS (2017)
Nanocluster irradiation evolution in Fe-9%Cr ODS and ferritic-martensitic alloys
M. J. Swenson et al.
JOURNAL OF NUCLEAR MATERIALS (2017)
Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy
Kevin G. Field et al.
JOURNAL OF NUCLEAR MATERIALS (2017)
Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa
Kevin G. Field et al.
JOURNAL OF NUCLEAR MATERIALS (2017)
Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel
Ce Zheng et al.
JOURNAL OF NUCLEAR MATERIALS (2017)
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
Kevin G. Field et al.
JOURNAL OF NUCLEAR MATERIALS (2017)
Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing
Maxim N. Gussev et al.
NUCLEAR ENGINEERING AND DESIGN (2017)
Design, properties, and weldability of advanced oxidation-resistant FeCrAl alloys
M. N. Gussev et al.
MATERIALS & DESIGN (2017)
Dislocation loop evolution during in-situ ion FeCrAl alloys
Jack C. Haley et al.
ACTA MATERIALIA (2017)
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
Samuel A. Briggs et al.
ACTA MATERIALIA (2017)
LAMDA: Irradiated-Materials Microscopy at Oak Ridge National Laboratory
Chad M. Parish et al.
MICROSCOPY AND MICROANALYSIS (2016)
Modeling radiation induced segregation in iron-chromium alloys
Oriane Senninger et al.
ACTA MATERIALIA (2016)
Uniform corrosion of FeCrAl alloys in LWR coolant environments
K. A. Terrani et al.
JOURNAL OF NUCLEAR MATERIALS (2016)
Roles of vacancy/interstitial diffusion and segregation in the microchemistry at grain boundaries of irradiated Fe-Cr-Ni alloys
Ying Yang et al.
JOURNAL OF NUCLEAR MATERIALS (2016)
Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature
Anne A. Campbell et al.
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS (2016)
Irradiation-enhanced α′ precipitation in model FeCrAl alloys
P. D. Edmondson et al.
SCRIPTA MATERIALIA (2016)
Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments
Kevin G. Field et al.
ACTA MATERIALIA (2015)
Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature
Todd R. Allen et al.
JOURNAL OF MATERIALS RESEARCH (2015)
Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys
Kevin G. Field et al.
JOURNAL OF NUCLEAR MATERIALS (2015)
Cyclic Corrosion and Chlorination of an FeCrAl Alloy in the Presence of KCl
N. Israelsson et al.
OXIDATION OF METALS (2015)
The mechanism of radiation-induced segregation in ferritic-martensitic alloys
Janelle P. Wharry et al.
ACTA MATERIALIA (2014)
Relationship between lath boundary structure and radiation induced segregation in a neutron irradiated 9 wt.% Cr model ferritic/martensitic steel
Kevin G. Field et al.
JOURNAL OF NUCLEAR MATERIALS (2014)
α′ precipitation in neutron-irradiated Fe-Cr alloys
Mukesh Bachhav et al.
SCRIPTA MATERIALIA (2014)
Effect of grain boundary orientation on radiation-induced segregation in a Fe-15.2 at.% Cr alloy
Rong Hu et al.
ACTA MATERIALIA (2013)
The effect of Al on the 475 °C embrittlement of Fe-Cr alloys
Wei Li et al.
COMPUTATIONAL MATERIALS SCIENCE (2013)
Microstructural evolution in proton irradiated NF616 at 773 K to 3 dpa
Y. Huang et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
A systematic study of radiation-induced segregation in ferritic-martensitic alloys
Janelle P. Wharry et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
Dependence on grain boundary structure of radiation induced segregation in a 9 wt.% Cr model ferritic/martensitic steel
Kevin G. Field et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
TEM characterization of dislocation loops in irradiated bcc Fe-based steels
B. Yao et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
Phase separation kinetics in a Fe-Cr-Al alloy
C. Capdevila et al.
ACTA MATERIALIA (2012)
Application of the inverse Kirkendall model of radiation-induced segregation to ferritic-martensitic alloys
Janelle P. Wharry et al.
JOURNAL OF NUCLEAR MATERIALS (2012)
A systematic approach for the study of radiation-induced segregation/depletion at grain boundaries in steels
Emmanuelle A. Marquis et al.
JOURNAL OF NUCLEAR MATERIALS (2011)
Radiation-induced segregation and phase stability in ferritic-martensitic alloy T 91
Janelle P. Wharry et al.
JOURNAL OF NUCLEAR MATERIALS (2011)
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic-martensitic alloys
Gary S. Was et al.
JOURNAL OF NUCLEAR MATERIALS (2011)
High temperature oxidation of Fe-Al and Fe-Cr-Al alloys: The role of Cr as a chemically active element
E. Airiskallio et al.
CORROSION SCIENCE (2010)
Effects of oversized solutes on radiation-induced segregation in austenitic stainless steels
M. J. Hackett et al.
JOURNAL OF NUCLEAR MATERIALS (2009)
Oxidation of FeCrAl foils at 500-900 degrees C in dry O-2 and O-2 with 40% H2O
J. Engkvist et al.
MATERIALS AT HIGH TEMPERATURES (2009)
Phase separation in PM 2000™ Fe-base ODS alloy:: Experimental study at the atomic level
C. Capdevila et al.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING (2008)
Irradiation-induced grain boundary chromium microchemistry in high alloy ferritic steels
Z. Lu et al.
SCRIPTA MATERIALIA (2008)
Simulation of thermal ageing and radiation damage in Fe-Cr
Janne Wallenius et al.
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS (2007)
Effect of hafnium on radiation-induced inter-granular segregation in ferritic steel
Z. Lu et al.
JOURNAL OF NUCLEAR MATERIALS (2006)
Microstructural evolution of proton irradiated T91
G. Gupta et al.
JOURNAL OF NUCLEAR MATERIALS (2006)
Modeling of chromium precipitation in Fe-Cr alloys
J Wallenius et al.
PHYSICAL REVIEW B (2004)
Application of focused ion beam lift-out specimen preparation to TEM, SEM, STEM, AES and SIMS analysis
FA Stevie et al.
SURFACE AND INTERFACE ANALYSIS (2001)
Numerical simulation modeling on the effects of grain boundary misorientation on radiation-induced solute segregation in 304 austenitic stainless steels
TS Duh et al.
JOURNAL OF NUCLEAR MATERIALS (2001)
Effects of grain boundary misorientation on solute segregation in thermally sensitized and proton-irradiated 304 stainless steel
TS Duh et al.
JOURNAL OF NUCLEAR MATERIALS (2000)
Atom probe studies of the Fe-Cr system and stainless steels aged at intermediate temperature: A review
F Danoix et al.
MATERIALS CHARACTERIZATION (2000)
Share Paper
