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Characterization of high active waste (155 GWd/Te) arising from fast reactor fuel reprocessing
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K. A. Venkatesan
Published/Copyright:
June 25, 2012
Abstract
A typical high active waste (HAW) arising from reprocessing of the nuclear fuel –(U0.3Pu0.7)C irradiated to the burn-up of 155 GWd/Te in a Fast Breeder Test Reactor (FBTR) was characterized by various analytical techniques. The target element was separated from other interferences or pre-concentrated by a suitable technique such as solvent extraction, chromatographic methods etc. The results obtained from various techniques are compared. The implications of the estimated composition in handling, treatment and disposal of HAW are discussed.
Published Online: 2012-06-25
Published in Print: 2012-11
© by Oldenbourg Wissenschaftsverlag, München, Germany
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Keywords for this article
Hight-active waste;
Characterization;
Gamma-spectometry;
ICP-AES;
Plutonium
Articles in the same Issue
- The influence of f-elements' oxidizing potential and ion charge on their stability in aqueous alkaline solution
- Adjustment of valence state of Pu and Np in nitric solution containing N,N-dimethylhydroxylamine and monomethylhydrazine by electrolysis
- Effect of crystal size on purity of uranyl nitrate hexahydrate crystalline particles grown in nitric acid medium
- Adsorption of tetravalent thorium by geomedia
- Studies on biosorption of Cr(VI) on a green resin: dry cow dung powder and tracer technique
- Characterization of high active waste (155 GWd/Te) arising from fast reactor fuel reprocessing
- Radiochemical analysis of concrete samples from accelerator waste
- 90Nb – a potential PET nuclide: production and labeling of monoclonal antibodies
- Production and separation of no-carrier-added 73As and 75Se from 7Li irradiated germanium oxide target
