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Analysis of radiation control in the storage of spent nuclear fuel at NPP Temelín
PAPAN, Juraj
Problems of dealing with radioactive materials, especially burnt out nuclear fuel, are a delicate and discussed topic in the Czech Republic and other advanced countries nowadays. In this work, the realization of radiation control of warehouse of burnt-out atomic fuel of nuclear power plant Temelín is analysed. Step by step there are stored packaging files filled with burnt-out fuel which is produced by the running of atomic reactors. In the introductory chapters individual packaging files are described. The shielding of stored burnt-out nuclear fuel and prevention of release of radionuclides beyond the protective casing of packaging files depend on their quality. Further the lo-cality of nuclear plant Temelín, where the warehouse of burnt-out nuclear fuel is placed including manipulations which are carried out with the packaging file, is described. The emphasis is placed on monitoring technological parameters during the storage of pack-aging files. The target of this work is to analyse the radiation control of warehouse of burnt-out nuclear fuel, precautions of radiation protection valid for this object and con-sider the possibility of optimalization of used measuring devices, suggest the adjustment of the way of carried out monitoring. For meeting the goals of this works it was neces-sary to carry out monitoring the current radiation situation in the storage boat which is partly filled with packaging spaces when according to the following calculations I ap-proached to the prediction of the level of radiation situation during the maximum filled storage boat. These calculations are at the same time the background for the proposal of adjustment of regime precautions in this object with the aim to optimise the professional radiation. One of the basic strategic targets of the operator of nuclear plant Temelín, company ČEZ a.s., is to ensure a safe operation of the biggest Czech nuclear plant, one of the basic conditions for meeting this target is to ensure the radiation control and pro-tection in the required quality. The results, which are the output of this work, will be given to the department Operation of radiation protection for other practical usage, pos-sible adjustment of a current operation documentation which solves the radiation control of the storage of burnt-out nuclear fuel.
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Measuring methods of surface contamination with radioactive substance in the nuclear power plant Temelin
PAPAN, Juraj
Monitoring of the occurrence and scope of surface contamination is performed by the Radiation Protection department in order to adopt adequate measures for the protection of persons from unwanted contamination and to inspect observation of limits for surface contamination and for items taken outside the controlled area. The chapter containing results and collected data includes a definition of the measured parameter and it stresses the surface contamination as a major health risk factor, which is demonstrated by conversion of surface contamination values into absorbed doses in the exposed body organs. This is followed by the principles, issues and factors affecting detection of ionizing radiation, particularly the surface activity, which is used to express the extent of surface contamination. The issues of detection are followed by a description of scope and principle of monitoring implementation within which the individual measurements are performed, taking into account the reference levels for specific measurements. The individual measuring procedures are accompanied with descriptions of their use. Apart from a summary description of the implementation of surface contamination monitoring in the nuclear power plant Temelín, one of the objectives of the thesis was the analysis of errors introduced into the measurement process by persons performing the measurements. The main objective of the thesis was to confirm the hypothesis that measures adopted by the Radiation Protection department, based on results from working measurements for the protection of workers who get into contact with radioactivity in form of surface contamination, are sufficient and that the limits for surface contamination of items taken outside the controlled area are not exceeded.
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