Laboratory scale separation of uranium from thorium in 1B extractor for the aqueous reprocessing of thorium-based spent fuel

Yuanxian Xia; Chengying Tao; Zhili Wu

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Laboratory scale separation of uranium from thorium in 1B extractor for the aqueous reprocessing of thorium-based spent fuel

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- Laboratory scale separation of uranium from thorium in 1B extractor for the aqueous reprocessing of thorium-based spent fuel
- Nuclear Techniques Vol. 10, Issue 2, (1987)
- 作者机构：
  
  中国科学院上海原子核研究所
- 作者简介：
- 基金信息：
- DOI：
  CLC：
- Received：26 December 1985，
  
  Published：1987-02
- 稿件说明：
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Yuanxian Xia, Chengying Tao, Zhili Wu. Laboratory scale separation of uranium from thorium in 1B extractor for the aqueous reprocessing of thorium-based spent fuel[J]. Nuclear techniques, 1987, 10(2): 22-26,62.
DOI：

Yuanxian Xia, Chengying Tao, Zhili Wu. Laboratory scale separation of uranium from thorium in 1B extractor for the aqueous reprocessing of thorium-based spent fuel[J]. Nuclear techniques, 1987, 10(2): 22-26,62. DOI：

摘要

本文研究了铀钍萃取分离条件。采用30%磷酸三丁酯（TBP）-煤油作补萃剂，稀硝酸作反萃剂，常温操作。应用串级实验，确定了1

槽的反萃段和补萃段的萃取理论级数、流比和反萃剂的酸度，同时测得了铀钍的净化系数。铀中去钍的分离系数

200，铀的收率

99.7%。

Abstract

In this paper the separation of uranium from thorium in 1B extractor for the acid thorex process was described. The operation of 1B extractor was carried out with 30%TBP-kerosene as scrubbing agent and dilute nitric acid as stripping agent at room temperature. The theoretical stages of the scrub section and strip section

the optimum conditions of the relative flow rates and acidity of the stripping agent were determined by means of batch-wise countercurrent extraction experiments. The decontamination factors for uranium and thorium was also determined

respectively. The separation coefficient of the uranium from thorium is more than 200

the recovery efficiency of the uranium is 99.8%.

关键词

Keywords

references

Technical Committee on the utilization of Thorium- Based Nucler fuel: Current status and prespectsves, IAEA—Tc—566 , Vienna, Austria 2—4 Dec 1985 .

Stoller and Richards ed., Reactor handbook , vol. 2 , 1961 , p. 208 .

F. R. Bruce , USAEC Report, T1D—7534 .

Stoller and Richards ed., Reactor handbook , vol. 2 , 1961 , p. 219 .

H. C. Rathron et al ., Pooc. of second Intern. Thorium fuel cycle symposium , Gatlinburg, Tennessee , 3—6 May, 1966 , p. 808 .

ibid , 765 .

R. H. Rainey et al ., USAEC Report , ORNL -3155 .

A. A. Kishbaush , USAEC Report DP —1022 .

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