National Repository of Grey Literature 3 records found  Search took 0.01 seconds. 
Spent nuclear fuel and its properties
Jestřáb, Tomáš ; Řež,, Martina Malá, Centrum výzkumu (referee) ; Katovský, Karel (advisor)
The main goal of this Bachelor’s thesis is to develop fuel depletion models of a nuclear fuel used at Nuclear Power Plant Dukovany – originally designed nonprofiled fuel used in a three-year cycle, inovated profiled fuel used in a four-year cycle and currently used fuel Gd-2M+ used in a five year fuel cycle. Models are created by computational code UWB1 providing fast calculation of nuclear fuel depletion. Outputs of these models are in thesis graphically displayed and analyzed from the point of view of fuel depletion, enrichment or irradiation time spent in reactor core. These analyses are based on theory including information about the nuclear fuel cycle focusing on its middle part and the back end of the nuclear fuel cycle.
Spent nuclear fuel and its properties
Jestřáb, Tomáš ; Řež,, Martina Malá, Centrum výzkumu (referee) ; Katovský, Karel (advisor)
The main goal of this Bachelor’s thesis is to develop fuel depletion models of a nuclear fuel used at Nuclear Power Plant Dukovany – originally designed nonprofiled fuel used in a three-year cycle, inovated profiled fuel used in a four-year cycle and currently used fuel Gd-2M+ used in a five year fuel cycle. Models are created by computational code UWB1 providing fast calculation of nuclear fuel depletion. Outputs of these models are in thesis graphically displayed and analyzed from the point of view of fuel depletion, enrichment or irradiation time spent in reactor core. These analyses are based on theory including information about the nuclear fuel cycle focusing on its middle part and the back end of the nuclear fuel cycle.
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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