Capturing of 129I at reprocessing of spent nuclear fuel from power plants
AbstractAbstract
[en] Sorbent on a basis of aluminium oxide impregnated by silver nitrate salt was used for the 129I capture during reprocessing of spent nuclear fuel at the RT-1 plant. Using adsorption columns decreased 129I discharge to the level of sensitivity of analysis. Industrial service of the iodine purification system at the RT-1 plant provided support for validity of the method and reliability of the chosen apparatus for the 129I capture
Original Title
Ulavlivanie 129I pri pererabotke otrabotavshego yadernogo topliva ehnergeticheskikh ustanovok
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5 refs., 1 tab.
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Journal Article
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Descriptors (DEC)
ALUMINIUM COMPOUNDS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CHALCOGENIDES, ENERGY SOURCES, FUELS, HALOGEN COMPOUNDS, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, IODINE ISOTOPES, ISOTOPES, MATERIALS, NITRATES, NITROGEN COMPOUNDS, NUCLEAR FACILITIES, NUCLEAR FUELS, NUCLEI, ODD-EVEN NUCLEI, OXIDES, OXYGEN COMPOUNDS, RADIOISOTOPES, REACTOR MATERIALS, SEPARATION PROCESSES, SILVER COMPOUNDS, SORPTION, TRANSITION ELEMENT COMPOUNDS, YEARS LIVING RADIOISOTOPES
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