Fabrication and microstructure characterization of inert matrix fuel based on yttria stabilized zirconia
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference21 articles.
1. Categorisation and priorities for future research on inert matrix fuels: An extended synthesis of the panel discussions
2. A New Fuel Material for Once-Through Weapons Plutonium Burning
3. Plutonium Incineration in LWR's by a Once-Through Cycle with a Rock-Like Fuel
4. Comparison of Pressurized Water Reactor Core Characteristics for 100% Plutonium-Containing Loadings
5. Conceptual studies for pressurised water reactor cores employing plutonium–erbium–zirconium oxide inert matrix fuel assemblies
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1. Optimizing synthesis strategies for the production of single-phase zirconates with Ce and Nd co-doping;MRS Advances;2024-02-08
2. Solubility of monoclinic and yttrium stabilized cubic ZrO2: Solution and surface thermodynamics guiding ultra-trace analytics in aqueous phase;Journal of Nuclear Materials;2021-03
3. Thermodynamic stability of the fluorite phase in the CeO2 − CaO − ZrO2 system;Journal of Nuclear Materials;2019-04
4. Mechanical properties of zirconia, doped and undoped yttria-stabilized cubic zirconia from first-principles;Journal of Physics and Chemistry of Solids;2018-11
5. Studies on the synthesis of nanocrystalline yttria powder by oxalate deagglomeration and its sintering behaviour;Ceramics International;2015-05
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