As an important part of the design and development of advanced nuclear fission and fusion reactors, nuclear materials research is focused on finding materials that will perform under the high temperatures, high radiation doses, and corrosive environments predicted for these reactors. Highly alloyed ferritic-martensitic steel alloys show promise as fuel cladding and reactor core structural materials for their high-temperature performance, resistance to swelling, embrittlement, and oxidation, and relatively low nuclear radioactivation. Microstructural damage due to irradiation, including dislocation loop and cluster formation, can affect the mechanical properties. The objective of this study is to correlate irradiation-induced damage in the m...
Fe-Cr ferritic/martensitic (F/M) steels have been proposed as one of the candidate materials for the...
The objective of this study is to evaluate the effect of irradiation on the strengthening mechanisms...
The realisation of nuclear fusion energy will require materials that can withstand high doses of ne...
With the rising global demand for low-cost clean energy, nuclear fission and fusion systems willbeco...
Ferritic/martensitic (F/M) alloys are good competitors for structural and fuel cladding applications...
Ferritic/martensitic steels are candidate materials for structural and cladding components d...
The growing global demand for energy will increasingly call upon fusion reactors and Generation IV n...
In this project, the post-irradiation microstructures and mechanical properties of two types of Fe-C...
A review of the microstructure of irradiated reduced activation ferritic/martensitic steels is prese...
As part of the solutions towards resolving the challenges in energy shortage and climate changes, ad...
This study concerns four high performance structural alloys designed to withstand the extreme temper...
Ferritic-martensitic (F-M) steels are considered as lead candidate structural materials for Generati...
Ion irradiation is often used to simulate the effects of neutron irradiation due to reduced activati...
As one of promising candidate materials for fuel claddings and structural components in the Gen-IV f...
Department of Nuclear EngineeringRadiation resistance of two advanced ferritic-martensitic steels, F...
Fe-Cr ferritic/martensitic (F/M) steels have been proposed as one of the candidate materials for the...
The objective of this study is to evaluate the effect of irradiation on the strengthening mechanisms...
The realisation of nuclear fusion energy will require materials that can withstand high doses of ne...
With the rising global demand for low-cost clean energy, nuclear fission and fusion systems willbeco...
Ferritic/martensitic (F/M) alloys are good competitors for structural and fuel cladding applications...
Ferritic/martensitic steels are candidate materials for structural and cladding components d...
The growing global demand for energy will increasingly call upon fusion reactors and Generation IV n...
In this project, the post-irradiation microstructures and mechanical properties of two types of Fe-C...
A review of the microstructure of irradiated reduced activation ferritic/martensitic steels is prese...
As part of the solutions towards resolving the challenges in energy shortage and climate changes, ad...
This study concerns four high performance structural alloys designed to withstand the extreme temper...
Ferritic-martensitic (F-M) steels are considered as lead candidate structural materials for Generati...
Ion irradiation is often used to simulate the effects of neutron irradiation due to reduced activati...
As one of promising candidate materials for fuel claddings and structural components in the Gen-IV f...
Department of Nuclear EngineeringRadiation resistance of two advanced ferritic-martensitic steels, F...
Fe-Cr ferritic/martensitic (F/M) steels have been proposed as one of the candidate materials for the...
The objective of this study is to evaluate the effect of irradiation on the strengthening mechanisms...
The realisation of nuclear fusion energy will require materials that can withstand high doses of ne...