検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

照射済高速中性子炉燃料からのセシウムの水及び希薄硝酸溶液に対する溶出特性

Elution properties of cesium contained within irradiated fast neutron reactor fuel in water and diluted nitric acid solution

中原 将海; 鍛治 直也; 野村 和則 

Nakahara, Masaumi; Kaji, Naoya; Nomura, Kazunori

晶析工程に関してPuとCsの化合物の生成抑制の観点から、原料液中のCsを減少させることが求められている。照射済核燃料中のCsを粗分離するため、純水及び希薄HNO$$_{3}$$における浸漬試験を行った。浸漬67時間後の純水及び0.1mol/dm$$^{3}$$ HNO$$_{3}$$における燃料粉末からのCsの溶出率は、それぞれ33.8及び38.3%であった。燃料溶解前に燃料粉末を純水もしくは希薄HNO$$_{3}$$溶液に浸漬させることによりCsを粗分離できる可能性を示した。

In terms of preventing the formation of Pu and Cs compound, Cs in the feed solution should decrease in the U crystallization process. In order to separate Cs contained within irradiated nuclear fuel, the immersion experiments were carried out with the pure water and diluted HNO$$_{3}$$ solution. The elusion ratio of Cs within the powdered fuel in the pure water and 0.1 mol/dm$$^{3}$$ HNO$$_{3}$$ solution after 67 h was 33.8 and 38.3%, respectively. The experimental results suggest a possible beneficial effect of Cs elusion by immersion of the powdered fuel in the pure water and diluted HNO$$_{3}$$ solution before the fuel dissolution process.

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.