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Vauchy, R.; 廣岡 瞬; 渡部 雅; 加藤 正人
Scientific Reports (Internet), 13, p.2217_1 - 2217_8, 2023/02
Using the hard-sphere model with the existing tabulated values of ionic radii to calculate the lattice parameters of minerals does not always match experimental data. An adaptation of this crystallographic model is proposed by considering the cations and anions as hard and soft spheres, respectively. We demonstrate the relevance of this hybrid model with fluorite and antifluorite-structured systems.
ceramicsVauchy, R.; 廣岡 瞬; 渡部 雅; 横山 佳祐; 砂押 剛雄*; 山田 忠久*; 中道 晋哉; 村上 龍敏
Ceramics International, 49(2), p.3058 - 3065, 2023/01
被引用回数：0 パーセンタイル：0.01(Materials Science, Ceramics)Pure and low 
-AlO
-SiO co-doped ceria specimens were prepared by conventional ceramic processing using powder metallurgy. The effect of co-doping on the microstructural and structural properties of cerium dioxide was investigated by means of optical microscopy, scanning electron microscopy, X-ray diffraction and Raman spectroscopy. The co-addition of alumina and silica promoted liquid phase sintering (LPS) and significantly contributed to grain growth, even in the small concentrations of the present study (1 wt% and 2 wt%). A glassy-look phase precipitated at the grain boundaries, characteristic of liquid phase sintering. The addition of dopants to the formulation greatly enhanced the grain growth process without disturbing the CeO structure.
, ThO, UO, PuO, and (U, Pu)O加藤 正人; 渡部 雅; 廣岡 瞬; Vauchy, R.
Frontiers in Nuclear Engineering (Internet), 1, p.1081473_1 - 1081473_10, 2023/01
This study evaluates oxygen self-diffusion and chemical diffusion coefficients of fluorite-type oxides CeO, ThO, UO, PuO, and (U, Pu) O using point defect concentration, oxygen vacancies, and interstitial oxygen. The self-diffusion coefficient changed in proportion to the 1/n power of oxygen partial pressure, which is similar to the oxygen partial pressure dependence of the defect concentration. All parameters used to represent the diffusion coefficients were determined, and the experimental data were accurately stated. The chemical diffusion coefficient was much higher at O/M = 2.00 than in low O/M oxides. In the reduction process, the chemical diffusion control rate was dominant, and a new phase with O/M = 2.00 was formed, and it expanded from the surface in the oxidation process from a low O/M ratio to O/M = 2.00.
Vauchy, R.; 廣岡 瞬; 松本 卓; 加藤 正人
Frontiers in Nuclear Engineering (Internet), 1, p.1060218_1 - 1060218_18, 2022/12
Diffusion phenomena in uranium-plutonium mixed oxides U
PuyO dictate the physicochemical properties of MOX nuclear fuel throughout manufacturing, irradiation and storage. More precisely, estimating the cation interdiffusion is paramount insofar as it dovetails with the actinide redistribution during sintering and under irradiation. In this paper, we propose a critical review of the existing experimental data of U and Pu interdiffusion coefficients in MOX fuel.
Vauchy, R.; 廣岡 瞬; 砂押 剛雄*; 加藤 正人
no journal, ,
Uranium plutonium mixed oxides (MOX) are used worldwide as fuel elements for different nuclear reactor technologies. The Oxygen to Metal ratio of these materials is a first order parameter influencing most of their thermal properties (from cation interdiffusion to melting point). By definition, the relative partial free energy of oxygen, abusively designated as oxygen potential, of U Pu mixed oxides corresponds to the relation between the activity of oxygen in the solid (hence the Oxygen to Metal ratio) and the oxygen partial pressure of the surrounding gas phase. This fundamental thermodynamical property is of prime importance as it can be used for tailoring the Oxygen to Metal ratio of fuels during their manufacturing and, or, to be implemented in performance codes. Studying the influence of some of the main fission products on the oxygen potential of MOX is needed to better understand its in pile behavior but also within the frame of developing a low decontamination reprocessing of spent nuclear fuels. Most of the elements (and their isotope declinations) of the Mendeleev s periodic table are produced when nuclear fuels are irradiated. Neodymium is one of the more abundant solid fission products (FPs) and is also known to be soluble within the fluorite structure. Due to its high fission yield, evaluating the effect of Nd incorporation on the thermal properties of MOX fuels is necessary. Up to now, no oxygen potential data of Nd doped uranium plutonium americium mixed oxides are published.
