Recovery of Protactinium from Irradiated Thorium Nitrate by Solvent Extraction

被引：0

作者：

Khokhlov, M. L. ^{[1
]}

Yakushin, A. P. ^{[1
]}

Fedorov, Yu. S. ^{[2
]}

Samonin, V. V. ^{[2
]}

Davidenko, V. D. ^{[3
]}

Kovalishin, A. A. ^{[3
]}

Pavlov, K. V. ^{[3
]}

Titarenko, Yu. E. ^{[3
]}

Kirsanov, A. S. ^{[3
,4
]}

Arkhipov, A. A. ^{[4
]}

Kotel'nyi, M. V. ^{[4
]}

机构：

[1] Khlopin Radium Inst, St Petersburg 194021, Russia

[2] St Petersburg State Inst Technol, Tech Univ, St Petersburg 190013, Russia

[3] Kurchatov Inst, Natl Res Ctr, Moscow 123182, Russia

[4] Moscow Polytech Univ, Moscow 107023, Russia

来源：

RADIOCHEMISTRY | 2025年 / 67卷 / 02期

关键词：

fusion neutron source blanket; thorium; protactinium; uranium-233; extraction; n-octanol; diisobutylcarbinol;

D O I：

10.1134/S106636222502002X

中图分类号：

O65 [分析化学];

学科分类号：

070302 ; 081704 ;

摘要：

The extractive recovery of protactinium from irradiated thorium nitrate as applied to the conditions of the fusion neutron source blanket was studied using n-octanol and diisobutylcarbinol as extractants. The degree of recovery of Pa-233 from a solution of irradiated thorium nitrate (600 g/dm(3)) in 3 M nitric acid in one contact exceeded 80%, and the separation factors from uranium and thorium were higher than 600 and 130000, respectively. To reduce the content of U-232 in U-233 (below 5 ppm), a flowsheet involving short irradiation of thorium nitrate and continuous extractive recovery of protactinium was suggested.

引用

页码：119 / 125

页数：7

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