Feasibility studies for production of 89Sr in the Fast Breeder Test Reactor (FBTR)

被引：11
|
作者：
Saha, Debasish [1 ]
Vithya, J. [1 ]
Kumar, G. V. S. Ashok [1 ]
Swaminathan, K. [1 ]
Kumar, R. [1 ]
Subramani, C. R. Venkata [1 ]
Rao, P. R. Vasudeva [1 ]
机构：
[1] Indira Gandhi Ctr Atom Res, Chem Grp, Div Fuel Chem, Kalpakkam 603102, Tamil Nadu, India
来源：
RADIOCHIMICA ACTA | 2013年 / 101卷 / 10期
关键词：
Sr-89; production; FBTR; Bone pain palliation; Sr-Y; Dissolution of Y2O3 pellet; TBP-HNO3; Ion exchange; GM counter; CARRIER-ADDED Y-86; BONE PAIN; SOLVENT-EXTRACTION; SEPARATION; PALLIATION; STRONTIUM; THERAPY; RADIOYTTRIUM; TARGETS; SAMPLES;
D O I：
10.1524/ract.2013.2055
中图分类号：
O61 [无机化学];
学科分类号：
070301 ; 081704 ;
摘要：
Sr-89, a pure beta emitter with half life of 50.53 d is used as its chloride solution for palliative care of bone metastases. This paper describes the feasibility studies that have been conducted at FBTR, IGCAR for production of this radionuclide using the Y-89(n, p)Sr-89 reaction. Yttria pellets were irradiated in a special subassembly at the core centre for a total of 73 d in two steps of 35 d and 38 d with a time gap of 38 d. The irradiated yttria target was dissolved in nitric acid and the bulk Y was separated by solvent extraction using the TBP-HNO3 complex. The Sr-89 fraction was purified using the cation exchange resin DOWEX 50Wx8 (100-200 mesh size) from the other radioactive impurities seen. The eluted Sr-89 fraction was assayed using a GM counting system. The Sr-89 activity produced in 1 g of yttria pellet was found to be 19 mCi.
引用
收藏
页码：667 / 673
页数：7
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