Impact of fission product (Ce, Sn, Sr, Se) oxides on UO2 oxidation to U3O8
W Han, J Gao, M Li, M Zhang, R Liu - Progress in Nuclear Energy, 2024 - Elsevier
In order to investigate the impact of fission products on the oxidation of spent fuel in the
cladding separation process, the oxidation behavior and kinetic mechanism of UO 2 and …
cladding separation process, the oxidation behavior and kinetic mechanism of UO 2 and …
Synthesis and feasibility studies of doping U at Ti site of Y 2 Ti 2 O 7 as a radioactive waste immobilization matrix
In pursuit of clean and green nuclear energy one of the major challenges is to effectively
immobilize the nuclear waste. In this context A2B2O7 type pyrochlore owing to its structural …
immobilize the nuclear waste. In this context A2B2O7 type pyrochlore owing to its structural …
Ionic radii in fluorites
R Vauchy, S Hirooka, T Murakami - Materialia, 2023 - Elsevier
The construction of the fluorite unit-cell from the ionic radii of the constitutive species is
proposed with the use of our hybrid model, considering flexible anion and cation radii. 24 …
proposed with the use of our hybrid model, considering flexible anion and cation radii. 24 …
A first-principles simulation study on solubility of La, Nd, Zr and Mo in UO2 and U3O8
Z Huang, L Ma, J Zhang, Q Zhou, L Yang… - Journal of Nuclear …, 2025 - Elsevier
Solubility of fission products (FPs) in spent nuclear fuels is a key issue in understanding their
performance. In this study, a detailed density functional theory study on solubility of La, Nd …
performance. In this study, a detailed density functional theory study on solubility of La, Nd …
Manufacturing and characterization of simulated fission product (FP)-doped uranium–plutonium mixed oxide solid solutions (FP= Zr, Nd, Sm, and Gd)
R Vauchy, S Hirooka, Y Horii, K Hayashizaki… - Journal of Alloys and …, 2025 - Elsevier
Seven uranium–plutonium mixed oxides (MOX) comprising 10 and 20 mol% of solid
simulated fission products (FPs) were prepared via powder metallurgy. Zirconium …
simulated fission products (FPs) were prepared via powder metallurgy. Zirconium …
X-ray diffraction and Raman spectroscopic studies on ThO2− UO2 solid solutions
In view of the vast resources of thorium in India, thorium-based fuel cycle has been
envisaged as one of the most promising options to meet sustainable energy requirements. In …
envisaged as one of the most promising options to meet sustainable energy requirements. In …
Structural, compositional and morphological characterization of Nd3+-substituted UO2 microspheres obtained by ICHTJ sol–gel technique
M Brykala, M Rogowski, T Smolinski - Nuclear Engineering and Design, 2024 - Elsevier
In the context of americium recycling, the Minor Actinides Bearing Blanket (MABB) concept is
being considered, involving the use of advanced fuel U-substituted Am 2 O 3 with a cubic …
being considered, involving the use of advanced fuel U-substituted Am 2 O 3 with a cubic …