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Interfaces under ion irradiation: growth and taming of nanostructures
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Joining of Oxide Dispersion Strengthened Steels for Advanced Reactors
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14 MeV nickel-ion irradiated HT-9 ferritic steel with and without helium pre-implantation
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December 1990 |
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Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix
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November 1973 |
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Microstructural examination of commercial ferritic alloys at 200 dpa
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October 1996 |
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Effects of grain boundary misorientation on the solute segregation in austenitic stainless steels
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October 1998 |
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The mechanism of radiation-induced segregation in ferritic–martensitic alloys
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Response of equal channel angular extrusion processed ultrafine-grained T91 steel subjected to high temperature heavy ion irradiation
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Radiation-induced Ostwald ripening in oxide dispersion strengthened ferritic steels irradiated at high ion dose
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Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments
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October 2020 |
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Selection of fuel cladding material for nuclear fission reactors
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Microstructural evolution in friction stir welding of nanostructured ODS alloys
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Dual-beam irradiation of friction stir spot welding of nanostructured ferritic oxide dispersion strengthened alloy
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September 2012 |
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Ion-irradiation effects on dissimilar friction stir welded joints between ODS alloy and ferritic stainless steel
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Influence of high dose neutron irradiation on microstructure of EP-450 ferritic–martensitic steel irradiated in three Russian fast reactors
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August 2004 |
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Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation
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March 2008 |
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Formation of Y2O3 nanoclusters in nano-structured ferritic alloys: Modeling of precipitation kinetics and yield strength
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Formation energy of vacancies in FeCr alloys: Dependence on Cr concentration
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January 2011 |
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Stability of nano-oxides upon heavy ion irradiation of an ODS material
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October 2011 |
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In situ TEM study of the stability of nano-oxides in ODS steels under ion-irradiation
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September 2012 |
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Microstructure and mechanical properties of friction stir welded oxide dispersion strengthened alloy
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January 2013 |
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Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel
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April 2013 |
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Carbon–vacancy complexes as traps for self-interstitial clusters in Fe–C alloys
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September 2013 |
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Irradiation response of ODS ferritic steels to high-energy Ne ions at HIRFL
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Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa
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October 2014 |
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Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9
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July 2015 |
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Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys
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Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation
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December 2015 |
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Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels
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November 2016 |
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The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels
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February 2017 |
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A review of the irradiation evolution of dispersed oxide nanoparticles in the b.c.c. Fe-Cr system: Current understanding and future directions
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April 2017 |
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Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations
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April 2017 |
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Molecular statics calculations of the biases and point defect capture volumes of small cavities
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February 2018 |
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Microstructure evolution of T91 irradiated in the BOR60 fast reactor
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June 2018 |
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The influence of helium on cavity evolution in ion-irradiated T91
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October 2018 |
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Effect of friction stir welding and self-ion irradiation on dispersoid evolution in oxide dispersion strengthened steel MA956 up to 25 dpa
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March 2019 |
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Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications
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February 2020 |
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Grain size and particle dispersion effects on the tensile behavior of friction stir welded MA956 oxide dispersion strengthened steel from low to elevated temperatures
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Friction stir welding and processing
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SRIM – The stopping and range of ions in matter (2010)
- Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
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Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12
https://doi.org/10.1016/j.nimb.2010.02.091
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June 2010 |
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Radiation response of oxide-dispersion-strengthened alloy MA956 after self-ion irradiation
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October 2017 |
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Emulation of reactor irradiation damage using ion beams
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October 2014 |
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On the use of transmission electron microscopy to quantify dislocation densities in bulk metals
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March 2020 |
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Atomic number dependence of Z contrast in scanning transmission electron microscopy
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August 2018 |
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Microstructures and ion-irradiation behaviour of friction stir welded 12Cr-ODS steel
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May 2017 |
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Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
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June 2017 |
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Cu-precipitation kinetics in α − Fe from atomistic simulations: Vacancy-trapping effects and Cu-cluster mobility
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Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment
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Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
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