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Effect of a nuclear power plant in terms of radiatin burden
Vániš, Jiří ; Procházka, Zdeněk (referee) ; Belatka, Martin (advisor)
This text deals with ionizing radiation affecting nuclear power plant personnel and surrounding population. Irradiation limits of radiological industry personnel are also mentioned along with ways of protecting them and checks on absorbed ionizing radiation dose. In conclusion, a nuclear power plant, as a source of ionizing radiation, and its effects on contamination of water sources and gas vents are evaluated. The next part be engaged problematical of storage nuclear waste from the time, when is removed the nuclear waste from nuclear reactor, trough permanent storage.
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Effect of a nuclear power plant in terms of radiatin burden
Vániš, Jiří ; Procházka, Zdeněk (referee) ; Belatka, Martin (advisor)
This text deals with ionizing radiation affecting nuclear power plant personnel and surrounding population. Irradiation limits of radiological industry personnel are also mentioned along with ways of protecting them and checks on absorbed ionizing radiation dose. In conclusion, a nuclear power plant, as a source of ionizing radiation, and its effects on contamination of water sources and gas vents are evaluated. The next part be engaged problematical of storage nuclear waste from the time, when is removed the nuclear waste from nuclear reactor, trough permanent storage.
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Bayesian Methods for Optimization of Radiation Monitoring Networks
Šmídl, Václav ; Hofman, Radek
Release of radioactive material into the atmosphere is the last possible resort of any accident in a nuclear power plant. It is an extremely rare event, however with severe consequences for potentially many people living in proximity of the power plant. Awareness of radiation security has been increased after the Chernobyl accident, and almost every country is now equipped with monitoring network of on-line connected receptors continually measuring radiation levels. Initial configurations of the network were designed by experts using their experience.In this report, we are concerned with local scale modeling of less severe accident in the range of tens of kilometers from the nuclear power plant. Both the stationary and mobile groups will be discussed. The preferred model of uncertainty is the empirical density which will be assimilated with measurements using the sequential Monte Carlo methodology. We will discuss influence of various loss functions.
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