Studies on separation and purification of fission 99Mo from neutron activated uranium aluminum alloy

被引：10
|
作者：
Rao, Ankita [1 ]
Sharma, Abhishek Kumar [2 ]
Kumar, Pradeep [1 ]
Charyulu, M. M. [1 ]
Tomar, B. S. [1 ]
Ramakumar, K. L. [1 ]
机构：
[1] Bhabha Atom Res Ctr, Radioanalyt Chem Div, Bombay 400085, Maharashtra, India
[2] Board Radiat & Isotope Technol, Navi Mumbai 400705, India
来源：
APPLIED RADIATION AND ISOTOPES | 2014年 / 89卷
关键词：
Mo-99; Fission products; Uranium-aluminum alloy; alpha-Benzoin oxime; Anion exchange; Radiochemical separation; GENERATORS;
D O I：
10.1016/j.apradiso.2014.02.013
中图分类号：
O61 [无机化学];
学科分类号：
070301 ; 081704 ;
摘要：
A new method has been developed for separation and purification of fission Mo-99 from neutron activated uranium-aluminum alloy. Alkali dissolution of the irradiated target (100 mg) results in aluminum along with Mo-99 and a few fission products passing into solution, while most of the fission products, activation products and uranium remain undissolved. Subsequent purification steps involve precipitation of aluminum as Al(OH)(3), iodine as AgI/AgIO3 and molybdenum as Mo-alpha-benzoin oxime. Ruthenium is separated by volatilization as RuO4 and final purification of Mo-99 was carried out using anion exchange method. The radiochemical yield of fission Mo-99 was found to be > 80% and the purity of the product was in conformity with the international pharmacopoeia standards. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码：186 / 191
页数：6
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