The management of radiation defects and insoluble He atoms represent key challenges for structural materials in existing fission reactors and advanced reactor systems. To examine how crystalline/amorphous interface, together with the amorphous constituents affects radiation tolerance and He management, we studied helium bubble formation in helium ion implanted amorphous silicon oxycarbide (SiOC) and crystalline Fe composites by transmission electron microscopy (TEM). The SiOC/Fe composites were grown via magnetron sputtering with controlled length scale on a surface oxidized Si (100) substrate. These composites were subjected to 50 keV He+ implantation with ion doses chosen to produce a 5 at% peak He concentration. TEM characterization show...
Oxide dispersion strengthened (ODS) alloys are considered as candidates for fuel assembly claddings,...
AbstractHelium implantation can cause the formation of a helium gas-bubble superlattice in crystalli...
AbstractThe microstructural changes of a tempered F82H ferritic–martensitic steel following He impla...
The management of radiation defects and insoluble He atoms represent key challenges for structural m...
The management of radiation defects and insoluble He atoms represent key challenges for structural m...
This study investigates the microstructural evolution and mechanical response of sputter-deposited a...
Damage caused by implanted helium (He) is a major concern for material performance in future nuclear...
Despite recent interest in amorphous ceramics for a variety of nuclear applications, many details of...
Temperature dependent He-irradiation-induced ion-beam mixing between amorphous silicon oxycarbide (S...
Through examination of radiation tolerance properties of amorphous silicon oxycarbide (SiOC) and cry...
A common goal for materials employed in nuclear environments is to exhibit the highest radiation tol...
Ni-SiOC nanocomposites maintain crystal-amorphous dual-phase nanostructures after high-temperature a...
Designing a material from the atomic level to achieve a tailored response in extreme conditions is a...
The properties of helium bubbles in a body-centred cubic (bcc) Fe lattice have been examined. The at...
Helium (He) bubbles are typical radiation defects in structural materials in nuclear reactors after ...
Oxide dispersion strengthened (ODS) alloys are considered as candidates for fuel assembly claddings,...
AbstractHelium implantation can cause the formation of a helium gas-bubble superlattice in crystalli...
AbstractThe microstructural changes of a tempered F82H ferritic–martensitic steel following He impla...
The management of radiation defects and insoluble He atoms represent key challenges for structural m...
The management of radiation defects and insoluble He atoms represent key challenges for structural m...
This study investigates the microstructural evolution and mechanical response of sputter-deposited a...
Damage caused by implanted helium (He) is a major concern for material performance in future nuclear...
Despite recent interest in amorphous ceramics for a variety of nuclear applications, many details of...
Temperature dependent He-irradiation-induced ion-beam mixing between amorphous silicon oxycarbide (S...
Through examination of radiation tolerance properties of amorphous silicon oxycarbide (SiOC) and cry...
A common goal for materials employed in nuclear environments is to exhibit the highest radiation tol...
Ni-SiOC nanocomposites maintain crystal-amorphous dual-phase nanostructures after high-temperature a...
Designing a material from the atomic level to achieve a tailored response in extreme conditions is a...
The properties of helium bubbles in a body-centred cubic (bcc) Fe lattice have been examined. The at...
Helium (He) bubbles are typical radiation defects in structural materials in nuclear reactors after ...
Oxide dispersion strengthened (ODS) alloys are considered as candidates for fuel assembly claddings,...
AbstractHelium implantation can cause the formation of a helium gas-bubble superlattice in crystalli...
AbstractThe microstructural changes of a tempered F82H ferritic–martensitic steel following He impla...