Separation of iodine produced from fission with a porous metal silver column in99Mo production
| Autor: | H. J. Cols, J. C. Furnari, P. R. Cristini, A. V. Mondino |
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| Rok vydání: | 1999 |
| Předmět: |
Nuclear fission product
Fission products Health Toxicology and Mutagenesis Radiochemistry Public Health Environmental and Occupational Health chemistry.chemical_element Uranium Pollution Analytical Chemistry law.invention Glass microsphere chemistry.chemical_compound Nuclear Energy and Engineering chemistry Sodium hydroxide law Molybdenum Radiology Nuclear Medicine and imaging Tellurium dioxide Distillation Spectroscopy |
| Zdroj: | Journal of Radioanalytical and Nuclear Chemistry. 240:731-734 |
| ISSN: | 1588-2780 0236-5731 |
| DOI: | 10.1007/bf02349845 |
| Popis: | In Argentina, at the Ezeiza Atomic Center,131I is produced by wet distillation of natural tellurium dioxide irradiated with thermal neutrons in a pool-type reactor. In order to recover the131I present in the production process of fission99Mo obtained by irradiation of UALx/Al targets (with 90% enriched uranium) a separation method was developed. Iodine isotopes can be separated from a sodium hydroxide solution containing fission products using a column filled with alternate beds of glass microspheres and porous metal silver. Tests with tracers were performed in radiochemical laboratory. Following this results, a series of tests with higher activities (3 TBq of99Mo and 0.7 TBq of131I) were carried out in hot cells. Molybdenum passes through the silver column, while131I retention was 92–97% in tracer test and 90% in optimised hot cell tests. This result depends on several facts that are discussed. An initial separation of iodine isotopes diminishes radiation damage on ion-exchange resin used in the subsequent molybdenum purification, improving its retention and elution yield. |
| Databáze: | OpenAIRE |
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