検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年
検索結果: 1 件中 1件目~1件目を表示
  • 1

発表形式

Initialising ...

選択項目を絞り込む

掲載資料名

Initialising ...

発表会議名

Initialising ...

筆頭著者名

Initialising ...

キーワード

Initialising ...

発表言語

Initialising ...

発行年

Initialising ...

開催年

Initialising ...

選択した検索結果をダウンロード

論文

Oxygen chemical diffusion in fast neutron reactor fuel U$$_{0.698}$$Pu$$_{0.289}$$Am$$_{0.013}$$O$$_{2-x}$$

Vauchy, R.; 堀井 雄太; 廣岡 瞬; 赤司 雅俊; 砂押 剛雄*; 中道 晋哉; 齋藤 浩介

Proceedings of 34th Nuclear Energy for New Europe (NENE2025) , p.232 - 238, 2026/01

The oxygen chemical diffusion of fast neutron reactor MOX U$$_{0.698}$$Pu$$_{0.289}$$Am$$_{0.013}$$O$$_{2-x}$$ was investigated by thermogravimetric analysis between 1773 and 1923 K, using an innovative experimental procedure. At a given temperature, the oxygen chemical diffusion coefficients were shown to decrease when the Oxygen/Metal ratio decreases (in hypo-stoichiometry). The variations of the oxygen chemical diffusion coefficients as a function of temperature and oxygen partial pressure (hence oxygen stoichiometry) were paralleled to a defect chemistry model.

1 件中 1件目~1件目を表示
  • 1