A detailed analysis technique for tritium recovery from contaminated graphite (similar to irradiated reactor graphite) was established using microwave acid digestion followed by liquid scintillation counting (LSC). Two types of liquid scintillation cocktails were tested. For an added tritium radioactivity of 8.874·10-4 Bq·L-1 (2.218·10+3 Bq per graphite sample), equivalent to tritium radioactivity in graphite wastes collected from thermal column

The aim of the present study is to investigate a method to evaluate the tritium activity in hydraulic oil waste generated during the operation of Romanian Cernavoda Nuclear Power Plant. The method is based on a combustion technique using the 307 PerkinElmer (R) Sample Oxidizer model. The hydraulic oil samples must be processed prior to counting to avoid color quenching (the largest source of inaccuracy) because these samples absorb in the region

A comparative study between solubilization and combustion methods used to prepare the organic solvent samples for liquid scintillation analyse is presented. The determination of tritium content in organic solvent waste generated during the operation of Romanian Cernavoda Nuclear Power Plant represents an important step in radioactive waste management. Liquid scintillation spectrometry is the most sensitive and widely used technique for tritium detection

The method applied to the evaluation of radiation activities implies sample preparation, liquid scintillation cocktail choosing, quench standard curve constructing and implementation, and results verification. We have constructed the quench curve using interpolation method by polynomial spline functions of three degree. In order to evaluate the measurement efficiencies of tritium activity in simulated liquid scintillation cocktail waste samples quench

The Ultima Gold scintillation liquid waste samples was counted in a 2100 TRI-CARB 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

The organic solvent-waste samples were counted in a 2100 TRI-CARB Packard model liquid scintillation analyzer using the "Ultima Gold F scintillation liquid" cocktail. Nine large sample/cocktail plastic vials were prepared. A homogeneous emulsion sample-cocktail was obtained by heating the nine vials on water-bath at 50 0C. Six sets of measurements were performed. The compensation procedure of the direct values with unequal measurement precisions

This paper describes a viable solidification technology to convert the liquid scintillation cocktail into a stable form which minimizes the probability to release tritium in the environment. This radioactive waste type is generated by the radio-chemical analysis lab of a CANDU nuclear power plant.

Organic liquid wastes (organic solvents solutions and liquid scintillation cocktails) were counted in a Model 2100 TR Packard TRI-CARB liquid scintillation analyzer. It was evaluated the performance of three commercially available liquid scintillation cocktails designed to measure tritium in organic samples. The non biodegradable cocktails don't exhibit higher efficiencies as well as the biodegradable cocktails. The Ultima Gold XR cocktail is suitable