• help
  • PC | SP
  • JP | EN
          
検索対象：     
報告書番号：
※ 半角英数字
 年 ～ 
 年
全てクリア
前の画面に戻る

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

高速中性子炉燃料U$$_{0.698}$$Pu$$_{0.289}$$Am$$_{0.013}$$O$$_{2-x}$$における酸素の化学拡散

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

Vauchy, R.; Horii, Yuta; Hirooka, Shun; Akashi, Masatoshi; Sunaoshi, Takeo*; Nakamichi, Shinya; Saito, Kosuke

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.

発表言語

 :

English

掲載資料名

 :

Proceedings of 34th Nuclear Energy for New Europe (NENE2025)

巻

 :

号

 :

ページ数

 :

p.232 - 238

発行年月

 :

2026/01

発表会議名

 :

34th Nuclear Energy for New Europe (NENE2025)

開催年月

 :

2025/09

開催都市

 :

Bled

開催国

 :

Slovenia

キーワード

 :

MOX Fuel; Oxygen diffusion; Manufacturing; Oxygen chemical diffusion coefficients; Defect chemistry

特許データ

 :

PDF

 :


論文URL

 :

研究データの公開先DOI

 :

本成果にかかわる研究データのリンクです。

使用施設

 :

広報プレスリリース

 :

論文解説
(JAEA R&D Navigator)

 :

受委託・共同研究相手機関

 :

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.

前の画面に戻る