検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

Experimental measurements of oxygen potential of neodymium doped MOX fuel

Vauchy, R.  ; 廣岡 瞬 ; 砂押 剛雄*; 加藤 正人   

Vauchy, R.; Hirooka, Shun; Sunaoshi, Takeo*; Kato, Masato

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.

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.