Study on solid solubility of Gd in UO2 using X-ray diffraction

Kapoor, K.; Rao, S Manimala; Sheela,; Sanyal, Tapobrata; Singh, Aman

doi:10.1016/s0022-3115(03)00239-3

Cited by 13 publications

(9 citation statements)

References 3 publications

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“…The XRD analysis performed on the (U, Gd)O2 pellets indicated the presence of only one crystalline phase in all samples. These results are not surprising considering that it has been previously reported that Gd 3+ can form a solid solution with UO2 in all composition ranges [79]. The obtained diffractograms are presented in Figure 3.8: It is well-known that the incorporation of trivalent lanthanide oxides in UO2 results in a contraction of the lattice parameter of the matrix, with the exception of La(III) [37,80,81].…”

Section: Pellet Characterizationsupporting

confidence: 62%

Study of hydrogen generation and radionuclide release during wet damaged oxide spent fuel storage

Gaiazov¹,

Komarov²,

Leshchenko³

et al. 2018

YadEn

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Section: Pellet Characterizationsupporting

confidence: 62%

Study of hydrogen generation and radionuclide release during wet damaged oxide spent fuel storage

Gaiazov¹,

Komarov²,

Leshchenko³

et al. 2018

YadEn

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“…However, whether or not this can be attributed to rare earth doping alone is dubious since the influence of dopants on the UO 2 lattice parameter has been shown to vary with the identity of the dopant. Kapoor et al43 observed a decrease in lattice constant when the dopant was Gd, whereas Wilson et al 44 reported an increase with La.…”

mentioning

confidence: 97%

Influence of Trivalent-Dopants on the Structural and Electrochemical Properties of Uranium Dioxide (UO₂)

Razdan

Shoesmith

2013

J. Electrochem. Soc.

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The influence of trivalent dopants (rare-earths, RE) on the structure, composition and electrochemical reactivity of UO 2 has been investigated using scanning electron microscopy (SEM/XRD), X-ray photoelectron spectroscopy (XPS), Raman spectroscopy and cyclic voltammetry (CV). This was achieved by comparing the behavior of undoped UO 2.002 , a slightly doped 1.5 at% SIMFUEL, and two rare-earth doped UO 2 (6 wt% Gd-UO 2 and 12.9 wt% Dy-UO 2 ) specimens. The reactivity decreased in the order UO 2.002 > SIMFUEL > Dy-UO 2 > Gd-UO 2 , showing that this decrease is a consequence of RE III doping. Raman spectroscopy showed this could be attributed to the formation of RE III -oxygen vacancy clusters whose formation decreases the availability of the vacancies required to accommodate the injection of oxygen interstitials during anodic oxidation. The behavior of SIMFUEL is complicated by the simultaneous formation of RE III -oxygen vacancy clusters and Zr-O 8 clusters.The safe disposal of spent nuclear fuel (SNF) is one of the key issues facing the modern nuclear power industry, and a major international effort is underway to develop safe management and disposal procedures. One potential management strategy in Canada is permanent disposal in a deep geologic repository. 1 The spent fuel would be sealed in metallic containers, emplaced in a repository and surrounded with compacted clay. The prospects for long term containment using copper containers are very good and corrosion models predict only minimal corrosion damage should be sustained. 2,3 However, if failure were to occur, contact of the fuel wasteform (uranium dioxide (UO 2 )) with groundwater would become possible. Although the solubility of UO 2 is very low under the anticipated anoxic conditions, radiolysis of the groundwater, due to the inherent radioactivity of the spent fuel, could lead to fuel corrosion, the U(IV) in the fuel being oxidized to the significantly more soluble U(VI) state. 4 This would make radionuclide release to the groundwater possible.Spent fuel is mainly UO 2 (> 95%), the remainder being the radioactive fission products and actinides produced during the in-reactor process. The inventory of radionuclides within the fuel depends on in-reactor burn-up and the linear power rating of the fuel. 5 Formation of these products leads to many physical and chemical changes within the fuel, 5 and post irradiation inspection of the fuel shows the presence of both volatile and non-volatile fission products. While volatile products may escape to the fuel-cladding gap, the non volatile products remain fixed within the fuel matrix in three distinct phases: the lanthanides in the fcc-fluorite lattice; the noble metals in metallic precipitates; and radionuclides unstable in the fluorite matrix in mixed metal oxides (perovskites). 6 The key changes likely to influence the chemical reactivity of the UO 2 matrix are the rare earth (RE) doping of the matrix and the development of non-stoichiometry. 7 Micro Raman spectroscopic studies show that non-stoichiometry lead...

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“…1), which was attributed to the lattice contraction with increasing gadolinium concentration already observed in previous studies. 8,19,[26][27][28][29] The results obtained by SEM-EDX and XRD showed that gadolinium was homogeneously distributed in the doped-UO 2 samples and, hence, the methodology used in this work for the synthesis of Gd 2 O 3 -doped UO 2 pellets was adequate.…”

Section: Characterisation Of Gd 2 O 3 -Uo 2 Samplesmentioning

confidence: 84%

Oxidative dissolution mechanism of both undoped and Gd₂O₃-doped UO₂(s) at alkaline to hyperalkaline pH

García-Gómez¹,

Giménez²,

Casas³

et al. 2023

Dalton Trans.

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Study on solid solubility of Gd in UO2 using X-ray diffraction

Cited by 13 publications

References 3 publications

Study of hydrogen generation and radionuclide release during wet damaged oxide spent fuel storage

Study of hydrogen generation and radionuclide release during wet damaged oxide spent fuel storage

Influence of Trivalent-Dopants on the Structural and Electrochemical Properties of Uranium Dioxide (UO₂)

Oxidative dissolution mechanism of both undoped and Gd₂O₃-doped UO₂(s) at alkaline to hyperalkaline pH

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Study on solid solubility of Gd in UO2 using X-ray diffraction

Cited by 13 publications

References 3 publications

Study of hydrogen generation and radionuclide release during wet damaged oxide spent fuel storage

Study of hydrogen generation and radionuclide release during wet damaged oxide spent fuel storage

Influence of Trivalent-Dopants on the Structural and Electrochemical Properties of Uranium Dioxide (UO2)

Oxidative dissolution mechanism of both undoped and Gd2O3-doped UO2(s) at alkaline to hyperalkaline pH

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Influence of Trivalent-Dopants on the Structural and Electrochemical Properties of Uranium Dioxide (UO₂)

Oxidative dissolution mechanism of both undoped and Gd₂O₃-doped UO₂(s) at alkaline to hyperalkaline pH