The results of the irradiation experiment MARIOS on americium transmutation

Elio, D'agata; Hania, P.R.; Béjaoui, S.; Sciolla, C.; Wyatt, T. R.; Hannink, M.H.C.; Herlet, Nathalie; Jankowiak, A.; Klaassen, F.M.; Lapetite, Jean‐Marc; Boomstra, D.A.; Phélip, M.; Delage, F.

doi:10.1016/j.anucene.2013.05.043

Cited by 21 publications

(6 citation statements)

References 4 publications

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“…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: 98%

Comparative XRPD and XAS study of the impact of the synthesis process on the electronic and structural environments of uranium–americium mixed oxides

Prieur

Lebreton

Martin

et al. 2015

Journal of Solid State Chemistry

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Section: Introductionmentioning

confidence: 98%

Comparative XRPD and XAS study of the impact of the synthesis process on the electronic and structural environments of uranium–americium mixed oxides

Prieur

Lebreton

Martin

et al. 2015

Journal of Solid State Chemistry

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“…The radiotoxicity and heat load of ultimate nuclear waste would thus be decreased as well as the ecological footprint of deep geological repositories [2,3]. In this context, several studies have been dedicated to U 1Àx Am x O 2±d compounds, not only to investigate synthesis methods [4][5][6][7][8][9][10][11] and assess their behaviour under irradiation in reactors [4,7,12,13], but also to determine their structural and thermophysical properties, the latter remaining scarcely known [14][15][16][17][18][19][20]. Among them, no data regarding the U 1Àx Am x O 2±d melting behaviour has been reported, despite the importance of such information with respect to safety margins during irradiation, notably in accidental conditions.…”

Section: Introductionmentioning

confidence: 99%

Melting behaviour of americium-doped uranium dioxide

Prieur

Lebreton

Caisso

et al. 2016

The Journal of Chemical Thermodynamics

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a b s t r a c t (Uranium + americium) mixed oxides are considered as potential targets for americium transmutation in fast neutron reactors. Their thermophysical properties and notably their melting behaviour have not been assessed properly although required in order to evaluate the safety of these compounds under irradiation. In this study, we measured via laser heating, the melting points under inert atmosphere (Ar) of U 1Àx Am x O 2±d samples with x = 0.10, 0.15, 0.20. The obtained melting/solidification temperatures, measured here, indicate that under the current experimental conditions in the investigated AmO 2 content range, the solidus line of the (UO 2 + AmO 2 ) system follows with very good agreement the ideal solution behaviour. Accordingly, the observed liquidus formation temperature decreases from (3130 ± 20) K for pure UO 2 to (3051 ± 28) K for U 0.8 Am 0.2 O 2±d . The melted and quenched materials have been characterised by combining X-ray diffraction and X-ray absorption spectroscopy.

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“…Even though irradiation experiments confirmed the feasibility of transmutation through the use of AmBB, consequent work is still needed before an actual industrial deployment. , In particular, the determination and quantification of elemental mechanisms during solid solution formation and the stability of the latter against α self-irradiation must be explored in detail.…”

Section: Introductionmentioning

confidence: 99%

New Insight into Self-Irradiation Effects on Local and Long-Range Structure of Uranium–Americium Mixed Oxides (through XAS and XRD)

et al. 2014

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Uranium-americium mixed oxides could be used as transmutation targets to lower Am inventory in spent nuclear fuels. Due to (241)Am activity, these materials are subjected to α-self-irradiation which provokes crystallographic disorder. Previous studies on U-Am mixed oxides gave first insight into α-radiation tolerance of these compounds, but have never been carried out for more than a year, whereas these compounds might be stored up to a few years between fabrication and irradiation. In this work, we study effects of self-irradiation on the structure of U(1-x)Am(x)O(2±δ) solid solutions (x = 0.15 and 0.20) aged 3 to 4 years. Especially, X-ray diffraction and X-ray absorption spectroscopy are combined to observe these effects from both long-range and local perspectives. Results show that the fluorite-type structure of U-Am mixed oxides withstands (241)Am α-irradiation without major damage. Despite the increase of interatomic distances and crystallographic disorder observed during the first months of storage, the present results show that a steady state is then reached. Thus, no detrimental factors have been identified in this study in terms of structural damage for several-year storage of U(1-x)Am(x)O(2±δ) pellets before irradiation. Furthermore, comparison between long-range and local evolution suggests that α-self-irradiation-induced defects are mainly located in low-ordered domains. Based on literature data and present results, the steady state appears related to the equilibrium between radioinduced defect formation and material self-healing.

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The results of the irradiation experiment MARIOS on americium transmutation

Cited by 21 publications

References 4 publications

Comparative XRPD and XAS study of the impact of the synthesis process on the electronic and structural environments of uranium–americium mixed oxides

Comparative XRPD and XAS study of the impact of the synthesis process on the electronic and structural environments of uranium–americium mixed oxides

Melting behaviour of americium-doped uranium dioxide

New Insight into Self-Irradiation Effects on Local and Long-Range Structure of Uranium–Americium Mixed Oxides (through XAS and XRD)

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