THE SAFETY OF ENVIRONMENT IN FINAL DISPOSAL OF ULTIMA GOLD SCINTILLATION LIQUID COCKTAIL USED FOR DETERMINATION OF THE RADIOACTIVE CONTENT IN VARIOUS SAMPLES AT CERNAVODA NUCLEAR POWER PLANT

摘要

The Ultima Gold scintillation liquid waste samples was counted in a 2100 TRI-CARB~R Packard model Liquid Scintillation Analyzer using the Ultima Gold XR scintillation liquid cocktail. To determine tritium content, three large sample/cocktail plastic vials were prepared and four sets of measurements were performed. Counting errors and statistics were applied on them to obtain specific activity of the waste. The immobilization and packaging of Ultima Gold liquid scintillation waste were carried out by cementation, using Portland cement and an adequate solidification additive in a standard dimension container. Radioactive waste packages produced comply with waste acceptance criteria developed by the National Commission for Nuclear Activities Control for disposal at the Baita National Repository, Bihor County, and thus the protection of human health and safety of the environment are ensured.