Solvent extraction behavior of minor nuclides in nuclear fuel reprocessing process

被引：13

作者：

Uchiyama, G ^{[1
]}

Asakura, T ^{[1
]}

Hotoku, S ^{[1
]}

Mineo, H ^{[1
]}

Kamei, K ^{[1
]}

Watanabe, M ^{[1
]}

Fujine, S ^{[1
]}

机构：

[1] Japan Atom Energy Res Inst, Proc Safety Lab, Tokai, Ibaraki 3191195, Japan

来源：

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2000年 / 246卷 / 03期

关键词：

Uranium; Plutonium; Nuclear Fuel; Technetium; Flow Sheet;

D O I：

10.1023/A:1006756215590

中图分类号：

O65 [分析化学];

学科分类号：

070302 ; 081704 ;

摘要：

The solvent extraction behavior of minor nuclides such as neptunium and technetium in a current PUREX process and an advanced PUREX process (PARC process) were studied by chemical flow sheet experiments using spent nuclear fuels. The uranium, plutonium, neptunium and technetium fractions distributed in the products and raffinates of the PARC process showed that n-butyraldehyde was an effective reductant of neptunium(VI) in the presence of uranium(VI) and plutonium(IV). It was also found that scrubbing with high acid concentration was effective for technetium separation.

引用

页码：683 / 688

页数：6

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