Abstract
The beta counting system uses a Geiger-Muller (GM) tube to detect the presence of beta contamination present in filter paper samples or in planchet samples. The counting system is enabled with a provision to count the samples at various distances from the detector to the sample position. The efficiency of the counting system is provided by the manufacturer at the time of procurement which is calibrated and tested using the standardized source. The user end has to be in conformity that the counting system responds to the radioactivity properly, since efficiency acts as the standard of comparison to check the healthiness of the detector. The paper brings out the practical experience gained while validating the efficiency of the counting system at various distances using the slit height adjustment. Key words: Efficiency, standardized source, counting system.
Highlights
The applications of nuclear techniques present a particular interest by monitoring the alpha and beta radioactive concentration from environmental factors, biological and food samples, ores samples, radioactive waste, phosphogypse deposits from industry, etc (Marian et al, 2013)
Uranium concentration in soil samples have been measured by two different methods (Baykara et al, 2007), besides, Kucukomeroglu et al (2008) investigated gross alpha/beta analyses in water by liquid scintillation counting (Wong et al, 2005) and in IAEA (2004) have measured radioactivity in sediments
The present study shows that the efficiency of the counting system will be higher when the height of the slit is chosen close to the detector
Summary
The applications of nuclear techniques present a particular interest by monitoring the alpha and beta radioactive concentration from environmental factors, biological and food samples, ores samples, radioactive waste, phosphogypse deposits from industry, etc (Marian et al, 2013). Uranium concentration in soil samples have been measured by two different methods (Baykara et al., 2007), besides, Kucukomeroglu et al (2008) investigated gross alpha/beta analyses in water by liquid scintillation counting (Wong et al, 2005) and in IAEA (2004) have measured radioactivity in sediments. In this type of nuclear applications, the characterization of gross alpha and beta radionuclide content (Zapata-Garcia et al., 2009) can be performed for various samples: solids, liquids, aerosols filters, etc. Radiation is non-sensory (Herman and Thomas, 2009) and the presence of radioactivity and radioactive material shall be identified by the use of radiation detection instruments only
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