Abstract
Some analytical procedures for the determination of tritium, strontium-90 and iodine-129 in liquid radioactive wastes from nuclear power plants of the type WWER-440 are described. Liquid scintillation counters (3H), beta-counters applying an Al-absorber (90Sr) and neutron activation analysis (129I) applying a suitable separation process are used. The results are discussed with respect to the waste management manufactured in future and the deposition of radioactive wastes coming from the nuclear power station “Kozloduj”.

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