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National Repository of Grey Literature 1 records found  Search took 0.01 seconds. 
Analysis methods of measurement of radioactive material during transports in the nuclear power plant
 PLAŇANSKÝ, Jiří
My bachelor´s work aims at analysing the existing method of measuring the input of the gama batch equivalent when trasporting radioactive material and verifying the possibility of using the portable scintillation spectrometer Inspector 1000 which, contrary to the presently used apparatus FH40G, has spectrometric properties and -due to its construction- even a faster response. At the beginning of my work there is a brief description of particular types of transporting radioactive material carried out within the operations in the Temelín nuclear power plant (ETE). The reader learns here about disposal solution of the way-in and way-out of the ETE as well as the types and conditions of transporting radioactive material. Further follows a description of principles how to detect ionizining radiation including a division of particular detector types. The work goes on with describing the presently used method of measuring the input of the gama batch equivalent and also presents a basic division of natural and artificial nuclides. In order to meet the aims of this bachelor´s work a comparative measurement including evaluation and comparison of the measured input values of the gama batch equivalent was made.. Based on these results I recommend to choose the apparatus Inspector 1000 for realisation of the ETE monitoring programme.
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