2013
DOI: 10.1016/j.jnucmat.2012.07.018
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Application of the UMACS process to highly dense U1−xAmxO2±δ MABB fuel fabrication for the DIAMINO irradiation

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Cited by 37 publications
(42 citation statements)
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“…The chemical compositions are presented in table 1 20 mol.%-Am samples were synthesized at Joint Research CentreInstitute for Transuranium Elements (JRC-ITU) using a process based on combination of (sol + gel) and infiltration methods to produce non-contaminant beads used as precursors for sintering [5,28]. The 15 mol.%-Am samples were prepared at Commissariat à ĺEnergie Atomique et aux énergies alternatives (CEA) from UO 2+d and AmO 2Àe starting powders (similar to those described in [7,8]) following the UMACS process based on two successive thermal treatments separated by a grinding step [7]. The sample characteristics are summarized in table 2.…”
Section: Sample Synthesismentioning
confidence: 99%
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“…The chemical compositions are presented in table 1 20 mol.%-Am samples were synthesized at Joint Research CentreInstitute for Transuranium Elements (JRC-ITU) using a process based on combination of (sol + gel) and infiltration methods to produce non-contaminant beads used as precursors for sintering [5,28]. The 15 mol.%-Am samples were prepared at Commissariat à ĺEnergie Atomique et aux énergies alternatives (CEA) from UO 2+d and AmO 2Àe starting powders (similar to those described in [7,8]) following the UMACS process based on two successive thermal treatments separated by a grinding step [7]. The sample characteristics are summarized in table 2.…”
Section: Sample Synthesismentioning
confidence: 99%
“…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%
“…nature of the precursor, milling step, etc. [4][5][6][7][8][9], the sintering steps are often performed in similar reducing conditions at high temperature (ca. 41600°C).…”
Section: Introductionmentioning
confidence: 99%
“…Despite this similarity of the final heat treatments, different values of O/M ratio have been reported for samples synthesized by solidliquid or solid-state chemistry. In the case of the U 1 À x Am x O 2 7 δ (x ¼0.10, 0.15 and 0.20) compounds fabricated by solid-state synthesis, it was shown that Am is strictly trivalent while U cations exhibit a mixed U þ IV/ þ V valence, whereby the Am þ III and U þ V contents were similar leading to overall O/M values close to 2.00 [6]. In contrast, the samples synthesized by liquid state chemistry (x ¼0.10 and 0.20), exhibited a mixed Am þ III/ þ IV valence and a U þ IV valence [11].…”
Section: Introductionmentioning
confidence: 99%
“…It consists in the irradiation Ambearing blankets (AmBB, i.e., U 1-x Am x O 2±δ with x values close to 10-15 at.%) in the periphery of a fast neutron reactor core. In this context, studies are being performed to assess the feasibility and safety of AmBB transmutation, notably focusing on innovative fabrication processes [1][2][3] Am being a strong α emitter (activity of 130 MBq), U 1-x Am x O 2±δ behavior under α self-irradiation is also monitored [6][7][8].…”
mentioning
confidence: 99%