Deformation behavior and irradiation tolerance of 316 L stainless steel fabricated by direct energy deposition
Additive manufacturing (AM) techniques have been widely used to fabricate structural
components with complex geometries. Understanding AM materials under extreme …
components with complex geometries. Understanding AM materials under extreme …
[HTML][HTML] Revealing hot deformation behavior of inconel X-750 superalloy: A novel hot processing map coupled with grain boundary engineering
J Zhang, Y Cao, Y Gong, J Xiao, Y Zhu, R Luo… - Journal of materials …, 2023 - Elsevier
In this work, a series of isothermal hot compression tests were performed at the temperature
of 900–1150° C with the strain rate ranging from 0.01 to 10s− 1 in Inconel X-750 alloy …
of 900–1150° C with the strain rate ranging from 0.01 to 10s− 1 in Inconel X-750 alloy …
First principle studies of effects of solute segregation on grain boundary strength in Ni-based alloys
Thermal annealing or radiation induced segregation of solute and impurity elements to grain
boundaries (GBs) in metallic alloys changes GB chemistry and thus can alter the GB …
boundaries (GBs) in metallic alloys changes GB chemistry and thus can alter the GB …
In-situ TEM investigation of unfaulting behavior of Frank loops in FCC Pd during H2+ & He+ dual-beam irradiation
Y Li, G Ran, Q Han, Y Xin, X Liu, X Ye - Scripta Materialia, 2021 - Elsevier
A faulted Frank dislocation loop (FDL) can transform into an unfaulted perfect dislocation
loop (PDL) under plastic deformation, quenching or particle irradiation. Here, we report our …
loop (PDL) under plastic deformation, quenching or particle irradiation. Here, we report our …
The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9
The microstructure and nanomechanical properties of three samples of the modified
stainless steel (referred as the alloy D9) were systematically characterized after neutron …
stainless steel (referred as the alloy D9) were systematically characterized after neutron …
Radiation response of a Fe–20Cr–25Ni austenitic stainless steel under Fe2+ irradiation at 500° C
The radiation response of a Fe–20Cr–25Ni austenitic stainless steel under self-ion
irradiation at 500° C was systematically investigated. The steel was irradiated at 500° C by …
irradiation at 500° C was systematically investigated. The steel was irradiated at 500° C by …
Combined effects of irradiation and hydrogen ions on surface oxidation of 308 L austenite stainless steel
The harsh environment in pressurized water reactor involving neutron irradiation and
hydrogen from the water radiolysis poses significant challenges on the passivation of …
hydrogen from the water radiolysis poses significant challenges on the passivation of …
Heavy ion irradiation response of an additively manufactured 316LN stainless steel
Additive manufacturing has become an appealing technique to fabricate three-dimensional
metallic materials and components for nuclear reactors. However, response of additively …
metallic materials and components for nuclear reactors. However, response of additively …
Measurement of grain boundary strength of Inconel X-750 superalloy using in-situ micro-tensile testing techniques in FIB/SEM system
Grain boundaries (GBs), known as two-dimensional defects, are omnipresent in
polycrystalline metallic alloys and thus influence a wide range of mechanical properties …
polycrystalline metallic alloys and thus influence a wide range of mechanical properties …
Investigating radiation-induced segregation on intragranular defects in a 316L (N)
S Rouland, B Radiguet, P Pareige - Journal of Nuclear Materials, 2021 - Elsevier
Radiation induced segregation (RIS) on lattice defects and phase stability under irradiation
have been investigated in an optimized solution annealed 316L (N) with an increased …
have been investigated in an optimized solution annealed 316L (N) with an increased …