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Ekstraksiyon Kromatografi İle Düşük Düzey Laboratuvar Atık Çözeltilerinden Uranyum Ayırımı

Ekstraksiyon kromatografisi, son yıllarda aktinitlerin ayrımı ve kazanımında uygulanmakta olan analitik bir tekniktir. Bu çalışmada, ekstraksiyon kromatografi tekniği ile düşük düzey radyoaktif atık çözeltisindeki uranyum(VI)' nın önderişimi ve ayrımı için bir metod geliştirilmiştir. Çalışmanın ilk kısmında, standart uranyum çözeltisi ile denemeler yapılmış olup, uranyum, trioktilfosfin oksit (TOPO) ile yüklü silika jel kolonda ekstrakte edilmiştir. Belirlenen optimum koşullarda, 1 M HNO3+1 M NaNO3 ortamında uranyumun ekstraksiyon verimi %99,5?1,5 bulunmuştur. Değişik elüsyon çözeltileri ile yapılan elüsyon denemelerinde en yüksek elüsyon verimleri; 0,5 M HCl çözeltisi için % 83,6, 0,5 M H3PO4 çözeltisi için %84,3, 1 M H3PO4 çözeltisi için %97,6 ve 9 M HClO4 çözeltisi için %92,3 olarak saptanmıştır. Metod doğrudan düşük düzey laboratuvar atık çözeltisine uygulandığında uranyum ekstraksiyon verimleri 3 M HNO3 için %52,8; 1 M HNO3+1 M NaNO3 için %67,3 olarak saptanmıştır. Atık çözeltisine 1:1 HClO4 ve %35' lik H2O2 ile önişlem yapıldığında, 1 M HNO3+1 M NaNO3ortamında uranyum ekstraksiyon verimi %95,7?2,3' ye ulaşmıştır. Kolondan önce, 0,5 M H2SO4 çözeltisi ile toryum % 89,2?3,1 ve daha sonra 9 M HClO4 çözeltisi ile uranyum %94,1?1,8 verim ile elüye edilmiştir

The Separation Uranium From Low Level Radioactivite Waste Solutions By Extraction Chromatography

In recent years, extraction chromatography is an analytical technique which is applied for the separation and recovery of actinides.In this study, a method for the preconcentation and separation uranium(VI) in low level radioactivite waste solution has been developed using extraction chromotograpy. In the first stage of the work, experiments were performend by standart uranium solutions and uranium was extracted on silica gel column coated with trioctylphosphine oxide. At determined optimum conditions, the yield of the uranium extraction in 1 M HNO3+1 M NaNO3 medium was found as 99.5?1.5%. Various stripping reactants tested in the experiments were as follows; 0.5 M HCl, 0.5 M H3PO4, 1 M H3PO4 and9 M HClO4, 83.6%, 84.3%, 97.6% and 92.3%,respectively. By applying this method to the low-level laboratory waste solutions, uranium extraction yields in 3 M HNO3 and 1 M HNO3+1 M NaNO3 were found as 52.8%, 67.3%, respectively. After the pretreatment with 4 mL 1:1 HClO4 and 6 mL 35% H2O2, the uranium extraction yield reached to 95.7?2.3% in 1 M HNO3+1 M NaNO3. Firstly, thorium was eluted with 10 mL 0.5 M H2SO4 and then uranium was eluted with 20 mL 9 M HClO4. The recoveries were 89.2?3.1% and 94.1?1.8%, respectively

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