National Repository of Grey Literature 2 records found  Search took 0.00 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.
Radionuclide detection in transported materials by a portable spectrometer.
PLAŇANSKÝ, Jiří
The aim of my diploma thesis was to assess possibilities of tracing and, consequently, identifying radionuclides in transported materials detected by detection frames on the protected area border of the nuclear power plant of Temelín, by means of the portable spectrometer Inspector 1000. To achieve this, I designed a series of measurements based on a simulated passage of a motor vehicle fitted with ionizining radiation sources of various activities at the designed points of measurement so that these measurements corresponded as close as possible to the actual passage of vehicles with large-sized loads. Recorded values were analysed and marginal activities for the particular measuring points were fixed. Computation correctness was then verified by another passage of the vehicle through the measuring device. Specified values of the marginal activities at the particular measuring points were, for comparison, consequently measured by the portable spectrometer Inspector 1000. Measurement results proved that the portable spectrometer Inspector 1000 can efficiently detect, identify and locate the sources of ionizing radiation causing the alarm level to be exceeded on a stable measuring device at the fixed measuring points, with a higher sensitivity than a stable measuring device. Conclusions of this diploma thesis will be given to the radiation protection unit of the nuclear power plant of Temelín as a basis for specification or even expansion of the methods of measuring ionizining radiation sources when transporting large-sized loads in the nuclear power plant, and their introduction into the monitoring programme.

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