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Naji, M. |
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Motta, Antonella |
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Aletan, Dirar |
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Mohamed, Tarek |
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Ertürk, Emre |
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Taccardi, Nicola |
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Kononenko, Denys |
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Petrov, R. H. | Madrid |
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Alshaaer, Mazen | Brussels |
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Bih, L. |
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Casati, R. |
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Muller, Hermance |
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Kočí, Jan | Prague |
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Šuljagić, Marija |
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Kalteremidou, Kalliopi-Artemi | Brussels |
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Azam, Siraj |
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Ospanova, Alyiya |
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Blanpain, Bart |
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Ali, M. A. |
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Popa, V. |
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Rančić, M. |
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Ollier, Nadège |
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Azevedo, Nuno Monteiro |
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Landes, Michael |
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Rignanese, Gian-Marco |
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Harrison, Robert W.
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (13/13 displayed)
- 2023Microstructure and radiation tolerance of molybdenum-rich glass composite nuclear waste formscitations
- 2023In situ TEM study of heavy-ion irradiation-induced amorphisation and electron beam-induced recrystallisation in powellite (CaMoO4)citations
- 2022Hydrotalcite colloid stability and interactions with uranium(VI) at neutral to alkaline pH.citations
- 2019Chemical effects on He bubble superlattice formation in high entropy alloyscitations
- 2019Local chemical instabilities in 20Cr-25Ni Nb-stabilised austenitic stainless steel induced by proton irradiationcitations
- 2019Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiationcitations
- 2019Intermetallic Re phases formed in ion irradiated WRe alloycitations
- 2019A Transmission Electron Microscopy study of the neutron-irradiation response of Ti-based MAX phases at high temperaturescitations
- 2018Enhanced radiation tolerance of tungsten nanoparticles to He ion irradiationcitations
- 2017Thermal Evolution of the Proton Irradiated Structure in Tungsten–5 wt% Tantalumcitations
- 2016Diffusion-based and creep continuum damage modelling of crack formation during high temperature oxidation of ZrN ceramicscitations
- 2014Nuclear Applications for Ultra-High Temperature Ceramics and MAX Phasescitations
- 2014Thermophysical characterisation of ZrCxNy ceramics fabricated via carbothermic reduction-nitridationcitations
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booksection
Nuclear Applications for Ultra-High Temperature Ceramics and MAX Phases
Abstract
Future nuclear reactor systems and the severe conditions under which they will operate are reviewed. Current nuclear applications of ceramics are predominantly as oxide fuels as well as ceramic/glassy waste forms, although non-oxides do find niche uses such as graphite moderators and B4C control rods. UHTCs properties of interest to the nuclear industry include that they may be fissile, and that they have high thermal conductivity, refractoriness, and phase stability. Using such properties, future nuclear ceramics will potentially include UHTCs, for example, as non-oxide fuels (U/Pu carbides and nitrides) and fuel cladding (TaC, ZrC, HfC). MAX phases may also find application as fuel cladding. Oxide and non-oxide composite (e.g., SiC/SiC) and inert matrix fuel systems are under development for future fission reactors while uses of ceramics in fusion reactor systems will be both functional (such as the ceramic superconductors in the magnet systems for controlling the plasma) and structural in various locations outside of the first wall in magnetic confinement fusion. Finally, the importance of thermodynamics in severe conditions and the need for accurate thermodynamics databases are highlighted.