Electrochemical recovery of plutonium from aqueous carbonate waste solutions

被引：2

作者：

Agarwal, Rahul ^{[1
,2
]}

Dumpala, Rama Mohana Rao ^{[3
]}

Sharma, Manoj K. ^{[1
,2
]}

Noronha, Donald M. ^{[2
]}

Gamare, Jayashree S. ^{[2
]}

Jayachandran, Kavitha ^{[1
,2
]}

Nandi, Chiranjit ^{[4
]}

Kaity, Santu ^{[4
]}

机构：

[1] Homi Bhabha Natl Inst, Mumbai 400094, Maharashtra, India

[2] Bhabha Atom Res Ctr, Fuel Chem Div, Mumbai 400085, Maharashtra, India

[3] Bhabha Atom Res Ctr, Radiochem Div, Mumbai 400085, Maharashtra, India

[4] Bhabha Atom Res Ctr, Radiomet Div, Mumbai 400085, Maharashtra, India

来源：

CHEMICAL COMMUNICATIONS | 2022年 / 58卷 / 08期

关键词：

URANIUM(V); SEPARATION; ACTINIDES; BEHAVIOR;

D O I：

10.1039/d1cc06603j

中图分类号：

O6 [化学];

学科分类号：

0703 ;

摘要：

Recovery of plutonium from aqueous carbonate waste solutions generated during the reprocessing of spent nuclear fuel is a key concern for sustainable nuclear energy programmes and the remediation of radioactive waste. Reported methods proceed through secondary waste generation caused by acidification of carbonate waste and make the recovery process cumbersome. Herein, we report a simple method for the recovery of Pu as solid PuO2 powder from carbonate waste solution in a two-step process. (i) Pu was selectively electrochemically precipitated as plutonium-hydroxide in the presence of interfering U, Th, Ru, Zr, Nb, Cs and the degradation products of tri-butyl phosphate by bulk electrolysis at -0.9 V using a Pt gauze electrode and (ii) the precipitate was annealed at 973 K for conversion to pure PuO2 powder. The present approach is simple, avoids the generation of secondary waste and reduces the exposure of working personnel to radiation.

引用

页码：1111 / 1114

页数：4

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