Analytical investigations of irradiated inert matrix fuel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference16 articles.
1. Categorisation and priorities for future research on inert matrix fuels: An extended synthesis of the panel discussions
2. Comparison of Pressurized Water Reactor Core Characteristics for 100% Plutonium-Containing Loadings
3. Conceptual studies for pressurised water reactor cores employing plutonium–erbium–zirconium oxide inert matrix fuel assemblies
4. Inert matrix fuel strategies in the nuclear fuel cycle: the status of the initiative efforts at the 8th Inert Matrix Fuel Workshop
5. The influence of carbonate complexes on the solubility of zirconia: new experimental data
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4. High-temperature stability of nanozirconate-toughed IMF material lanthanum synthesized by anin situreaction;RSC Advances;2019
5. Chemical state and atomic scale environment of nickel in the corrosion layer of irradiated Zircaloy-2 at a burn-up around 45 MWd/kg;Corrosion Science;2018-10
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