Canadian experience in irradiation and testing of MOX fuel
| Autor: | M.R. Floyd, S. Yatabe, F. Dimayuga |
|---|---|
| Rok vydání: | 2018 |
| Předmět: |
Nuclear and High Energy Physics
Materials science 020209 energy Metallurgy chemistry.chemical_element 02 engineering and technology 010403 inorganic & nuclear chemistry 01 natural sciences 0104 chemical sciences Plutonium Grain growth Nuclear Energy and Engineering chemistry Pellet 0202 electrical engineering electronic engineering information engineering Zirconium oxide Mixed oxide General Materials Science Irradiation MOX fuel |
| Zdroj: | Journal of Nuclear Materials. 502:177-190 |
| ISSN: | 0022-3115 |
| DOI: | 10.1016/j.jnucmat.2018.02.015 |
| Popis: | Experimental irradiation and performance testing of Mixed OXide (MOX) fuel at the Canadian Nuclear Laboratories (CNL) has taken place for more than 40 years. These experiments investigated MOX fuel behaviour and compared it with UO2 behaviour to develop and verify fuel performance models. This article compares the performance of MOX of various concentrations and homogeneities, under different irradiation conditions. These results can be applied to future fuel designs. MOX fuel irradiated by CNL was found to be comparable in performance to similarly designed and operated UO2 fuel. MOX differs in behaviour from UO2 fuel in several ways. Fission-gas release, grain growth and the thickness of zirconium oxide on the inner sheath appear to be related to MOX fuel homogeneity. Columnar grains formed at the pellet centre begin to develop at lower powers in MOX than in UO2 fuel. |
| Databáze: | OpenAIRE |
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