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Assesment of radiation protection in DIAMO state enterprise
ŠIMÁČKOVÁ, Eva
The importance of possible consequences of radiation, possible health hazard of people and the radionuclide contamination of the environment requires securing radiation protection from the very start of any operation, where radioactive substances are being handled with. One of these fields is the uranium industry in which DIAMO, state enterprise, takes an important position, dealing with the extraction and treatment of uranium, effacing the impacts of mining, remediation and disposal. Findings in the field of uranium industry are primarily won in form of research of professional information sources. In the theoretical part of the work, historical data about the founding and development of the organisation DIAMO, state enterprise, about carried out operations and the affect on the environment are being listed. Furthermore, information concerning radiation protection, its history, principles and measures are being elaborated. On the basis of carried out analysis and gauging results the level of secured radiation protection in DIAMO, state enterprise, is being assessed. Comparing the analysis of currently valid legal regulations to the analysis of safety documentation worked out in DIAMO, state enterprise, the fulfilment of requirements of legal standards is being assessed. In areas affected with uranium industry (Příbram, Stráž pod Ralskem, Mydlovary) gauging the dose equivalent power consupmtion of gama radiation has been carried out. In selected sites water and soil samples have been taken to assess the concentration of radionuclides. The results of the research are being compared to the measuremet results from other sources. In conclusion it is possible to state that the results in the carried out research are comparable to the results of similar researches carried out in other countries.
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Devices of radiation protection on the new nuclear source
LEŠTINA, Lukáš
The aim of the bachelor thesis is mapping the market with portable radiation protection devices offered by manufacturers specialized in nuclear measurement electronics, like Thermo Scientific, Canberra Packard and VF Černá Hora and subsequent comparison of for the purpose of finding operationally optimal solution of portable instrument for measurement of radiation quantities on a new nuclear source. At the beginning the reader is familiarized with occurrence of ionizing radiation, physical principles the instruments are based on and the radiation quantities by which the instruments interpret the final values. There is a description of the present state of portable measurement technologies used by radiation protection staff at Temelín Nuclear Plant. The description includes basic information, photos and specifications. A methodology with criteria of selection of new portable instruments was elaborated upon experience with the plant operation. Selected instruments from the large range by nuclear electronics manufacturers are described in an extra chapter. The discussion focuses on user comfort and suitability of the instruments based on the real situation of Temelín Nuclear Plant. Attention is also paid to versatility of the instruments and possibilities of their extension by additional devices like external probes of dose equivalent input, surface contamination or probes measuring dose equivalent input of neutrons. The instruments should correspond to the needs of the radiation protection staff as much as possible, so as they are able to fulfil the programme of monitoring on a new nuclear source in the most efficient manners.
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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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