2012
DOI: 10.1016/j.nucengdes.2011.10.016
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MARIOS: Irradiation of UO2 containing 15% americium at well defined temperature

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Cited by 14 publications
(5 citation statements)
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“…In the case of hypostoichiometric oxides, oxygen vacancies are expected to be the dominant defects. For both materials, the coordination value of the Me−Me shell is equal to 11.9 (5), indicating that the cation sublattice is not significantly affected by the sintering atmosphere, which would be expected.…”
Section: Resultsmentioning
confidence: 70%
See 1 more Smart Citation
“…In the case of hypostoichiometric oxides, oxygen vacancies are expected to be the dominant defects. For both materials, the coordination value of the Me−Me shell is equal to 11.9 (5), indicating that the cation sublattice is not significantly affected by the sintering atmosphere, which would be expected.…”
Section: Resultsmentioning
confidence: 70%
“…Thus, Am is fissioned into short-lived isotopes in neutron flux. Because UO 2 is the most widely used fuel and there is already a strong database on its behavior under neutron irradiation, U 1– y Am y O 2– x materials have been studied for this purpose in the past few years , and test irradiation programs are ongoing. , Generally, Am contents of about 20% are considered because higher compositions can result in unsatisfactory sodium compatibility. Two recent X-ray absorption spectroscopy (XAS) studies have indicated that Am is strictly Am III in Am-bearing UO 2 solid solutions.…”
Section: Introductionmentioning
confidence: 99%
“…The structure of such compounds can thus be approximatively described based on those respectively reported for PuO 2−δ and UO 2+ε domains. Recent studies showed, however, that the case of U 1– x Am x O 2±δ compounds (currently investigated for potential use as americium-bearing transmutation targets for nuclear waste long-term radiotoxicity attenuation) was different. Despite the similarities between plutonium and americium oxides (both exist for O/M ratios ranging from 1.5 to 2 with similar phase diagrams in the corresponding domains) and thus the stability of americium as both Am III+ and Am IV+ , several studies showed that Am III+ and U V+ cations coexist in single-phase U 1– x Am x O 2±δ compounds. Using X-ray absorption near-edge spectroscopy (XANES), Prieur et al.…”
Section: Introductionmentioning
confidence: 99%
“…This option abates the long time scale influence of MAs in the waste by their separation from the spent fuel, their incorporation in new fuels and their irradiation in fast neutron reactors, where they are converted by fission to fission products, with in the main a much shorter half life. In this framework, U 1 À x Am x O 2 7 δ compounds are studied increasingly as promising materials for americium recycling in fast reactor systems [2,3]. The Am content will most likely be x r0.…”
Section: Introductionmentioning
confidence: 99%