Perspectives on multiscale modelling and experiments to accelerate materials development for fusion
Prediction of material performance in fusion reactor environments relies on computational
modelling, and will continue to do so until the first generation of fusion power plants come on …
modelling, and will continue to do so until the first generation of fusion power plants come on …
Small scale mechanical testing of irradiated materials
P Hosemann, C Shin, D Kiener - Journal of Materials Research, 2015 - cambridge.org
Small specimen testing techniques have a long history in nuclear material research due to
the limitations posed by nuclear facilities. The limited space in reactors and the fact that the …
the limitations posed by nuclear facilities. The limited space in reactors and the fact that the …
Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels
The void swelling and microstructure evolution of ferritic-martensitic alloys HT9, T91 and T92
were characterized following irradiation with Fe++ ions at 460° C to damage levels of 75 …
were characterized following irradiation with Fe++ ions at 460° C to damage levels of 75 …
Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations
FeCrAl ferritic alloys are excellent cladding candidates for accident tolerant fuel systems due
to their high resistance to oxidation as a result of formation of a protective Al 2 O 3 scale at …
to their high resistance to oxidation as a result of formation of a protective Al 2 O 3 scale at …
Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9
Observations from a scanning electron microscopy examination of irradiated U-10Zr fuel are
presented. The sample studied had a local burnup of 5.7 atom percent and a local inner …
presented. The sample studied had a local burnup of 5.7 atom percent and a local inner …
Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy
A high-purity binary alloy Fe18Cr was subjected to heavy-ion irradiation in order to provide
improved understanding of the irradiation effect on radiation hardening associated with …
improved understanding of the irradiation effect on radiation hardening associated with …
[HTML][HTML] Irradiation effects of HT-9 martensitic steel
Y Chen - Nuclear Engineering and Technology, 2013 - Elsevier
High-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear
energy systems. Thanks to its excellent thermal conductivity and irradiation resistance …
energy systems. Thanks to its excellent thermal conductivity and irradiation resistance …
Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent …
In this study, the microstructure of a 12Cr ferritic-martensitic oxide-dispersion-strengthened
(ODS) alloy is studied before and after Fe ion irradiation up to 200 peak displacements per …
(ODS) alloy is studied before and after Fe ion irradiation up to 200 peak displacements per …
Microstructure evolution of T91 irradiated in the BOR60 fast reactor
Microstructures of T91 neutron irradiated in the BOR60 reactor at five temperatures between
376° C and 524° C to doses between 15.4 and 35.1 dpa were characterized using …
376° C and 524° C to doses between 15.4 and 35.1 dpa were characterized using …
Mechanism-based modeling of thermal and irradiation creep behavior: An application to ferritic/martensitic HT9 steel
In this work, the creep behavior of HT9 steel in both thermal and irradiation environments is
predicted using an integrated modeling framework. Multiple physical mechanisms such as …
predicted using an integrated modeling framework. Multiple physical mechanisms such as …