Recovery of 99mTc from Na2[99Mo]MoO4 solution obtained from reactor-produced (n,gamma) 99Mo using a tiny Dowex-1 column in tandem with a small alumina column.
A simple separation technique of (99m)Tc from Na(2)[(99)Mo]MoO(4) in sodium hydroxide solution obtained from the (98)Mo(n,gamma)(99)Mo reaction is described. Low to medium specific activity (99)Mo-molybdate solution of 7.4-18.5GBq (200-500mCi) in sodium hydroxide was passed through a tiny Dowex-1 column (25mg) to separate the (99m)Tc from the (99)Mo; subsequently the (99m)Tc was eluted from the Dowex 1 column with tetrabutylammonium bromide (TBAB) solution (1mg/5ml methylene chloride). The TBAB solution was passed through a small alumina column (1.5g) where the (99m)Tc is retained and separated from TBAB and CH(2)Cl(2). Technetium-99m from the alumina column was finally eluted with 5ml saline leaving any traces of (99)Mo on the alumina column. The separation yield was about 90% (n=10). The method has applicability for decontamination of (99g)Tc from spent (99)Mo waste solution and recovery of (99g)Tc for research use. The procedure should also be equally applicable for recovery of (188)ReO(4) from (188)WO(4) in a radioisotope laboratory.
Chattopadhyay
Sankha
S
Radiopharmaceuticals Laboratory, Regional Centre, Board of Radiation and Isotope Technology, Variable Energy Cyclotron Centre, Kolkata, West Bengal, India. sankha@veccal.ernet.in
Das
Sujata Saha
SS
Das
Malay K
MK
Goomer
Naresh C
NC
D000537:Aluminum Oxide / Q000737:chemistry*; D002852:Chromatography, Ion Exchange / Q000379:methods*; D005720:Gamma Rays; D008982:Molybdenum / Q000737:chemistry* / Q000528:radiation effects*; D009688:Nuclear Reactors; D011868:Radioisotopes / Q000737:chemistry*; D012117:Resins, Synthetic / Q000737:chemistry*; D012996:Solutions; D013667:Technetium / Q000737:chemistry* / Q000302:isolation & purification*
D011868:Radioisotopes; D012117:Resins, Synthetic; D012996:Solutions; D013667:Technetium; D008982:Molybdenum; C036240:Dowex 1X2; D000537:Aluminum Oxide