Feasibility studies for production of 89Sr in the Fast Breeder Test Reactor (FBTR)
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Debasish Saha
, J. Vithya , G. V. S. Ashok Kumar , K. Swaminathan , R. Kumar , C. R. Venkata Subramaniund P. R. Vasudeva Rao
Summary
89Sr, 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 89Y(n, p)89Sr 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 89Sr fraction was purified using the cation exchange resin DOWEX 50W×8 (100-200 mesh size) from the other radioactive impurities seen. The eluted 89Sr fraction was assayed using a GM counting system. The 89Sr activity produced in 1 g of yttria pellet was found to be 19 mCi.
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- Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections: integral tests of differential cross sections of neutron threshold reactions
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- Structure and spectroscopy of uranyl salicylaldiminate complexes
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- Effect of temperature on the solubility and solid phase stability of zirconium hydroxide
- Purification of selenium from thorium, uranium, radium, actinium and potassium impurities for low background measurements
- Analysis of long-lived radionuclides produced by proton irradiation in lead targets – γ -measurements
- Feasibility studies for production of 89Sr in the Fast Breeder Test Reactor (FBTR)
- Synthesis of I-131 labelled iodine species relevant during severe nuclear accidents in light water reactors
Artikel in diesem Heft
- Inhalt
- Cross-sections of 45Sc(n, 2n)44m,gSc reaction from the reaction threshold to 20 MeV
- Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections: integral tests of differential cross sections of neutron threshold reactions
- Determination of 234U and 238U in seawater samples by alpha spectrometry after concentration of U(VI) onto hydrotalcite and co-precipitation with LaF3
- Substitution of IO3 −, IO4−, SeO3 2−, and SeO42− for CO32− in Na4[UO2(CO3)3]
- Structure and spectroscopy of uranyl salicylaldiminate complexes
- A comparison between the chemical behaviour of lead-gold and lead-bismuth eutectics towards 316L stainless steel
- Effect of temperature on the solubility and solid phase stability of zirconium hydroxide
- Purification of selenium from thorium, uranium, radium, actinium and potassium impurities for low background measurements
- Analysis of long-lived radionuclides produced by proton irradiation in lead targets – γ -measurements
- Feasibility studies for production of 89Sr in the Fast Breeder Test Reactor (FBTR)
- Synthesis of I-131 labelled iodine species relevant during severe nuclear accidents in light water reactors