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

页码：186 / 191

页数：6

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