Interaction of extended dislocations with nanovoid clusters
Voids of nanoscale dimensions in irradiated metals can act as obstacles to dislocation
motion and cause strengthening. In this work, nanovoid strengthening and the influences of …
motion and cause strengthening. In this work, nanovoid strengthening and the influences of …
Grain orientation dependence of nanoindentation and deformation-induced martensitic phase transformation in neutron irradiated AISI 304L stainless steel
We studied the mechanical properties of a neutron irradiated AISI 304L stainless steel using
nanoindentation with respect to crystallographic grain orientation. After neutron …
nanoindentation with respect to crystallographic grain orientation. After neutron …
[HTML][HTML] Defect Production, evolution, and thermal recovery mechanisms in radiation damaged tungsten
Tungsten (W) is a prime candidate for use in plasma-facing components in fusion reactors.
These components are subjected to high temperatures and displacement damages caused …
These components are subjected to high temperatures and displacement damages caused …
Meso-timescale atomistic simulations on coalescence process of He bubbles in Fe by SEAKMC method
He bubbles are characteristic microstructures under fusion reactor conditions. They
approach and coalesce through their own migration, which significantly impacts the …
approach and coalesce through their own migration, which significantly impacts the …
Swelling resistance of advanced austenitic alloy A709 and its comparison with 316 stainless steel at high damage levels
Alloy A709 is an austenitic alloy developed for power boiler applications in thermal power
plants and is being considered as a candidate structural material for Generation IV reactors …
plants and is being considered as a candidate structural material for Generation IV reactors …
Role of cavities on deformation-induced martensitic transformation pathways in a laser-welded, neutron irradiated austenitic stainless steel
The role of cavities on deformation-induced martensitic phase transformations is studied in a
laser-welded and neutron irradiated austenitic stainless steel. Orientation dependent …
laser-welded and neutron irradiated austenitic stainless steel. Orientation dependent …
Microstructure and microchemistry of laser welds of irradiated austenitic steels
This article investigates the integrity of laser welds on neutron irradiated, He-containing
steels. Life extension of the current fleet of light water reactors could necessitate repair of …
steels. Life extension of the current fleet of light water reactors could necessitate repair of …
Correlative STEM-APT characterization of radiation-induced segregation and precipitation of in-service BWR 304 stainless steel
Radiation induced segregation and precipitation phenomena in an in-service boiling water
reactor 304 stainless steel component were investigated using directly correlated 3D-atom …
reactor 304 stainless steel component were investigated using directly correlated 3D-atom …
Interaction mechanism of an edge dislocation with a void in Fe–Ni–Cr concentrated solid-solution alloy
YK Dou, H Cao, XF He, J Gao, J Cao… - Journal of Alloys and …, 2021 - Elsevier
Abstract The interactions of a 1/2< 110>{111} edge dislocation with a void in Fe10Ni20Cr
and Fe33Ni33Cr concentrated solid-solution alloys are investigated by using molecular …
and Fe33Ni33Cr concentrated solid-solution alloys are investigated by using molecular …
Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates
Y Dong, BH Sencer, FA Garner, EA Marquis - Journal of Nuclear Materials, 2015 - Elsevier
AISI 304 stainless steel was irradiated at 416° C and 450° C at a 4.4× 10− 9 and 3.05× 10−
7 dpa/s to∼ 0.4 and∼ 28 dpa, respectively, in the reflector of the EBR-II fast reactor. Both …
7 dpa/s to∼ 0.4 and∼ 28 dpa, respectively, in the reflector of the EBR-II fast reactor. Both …