Přepravní kontejner pro radioaktivní odpady

Abstract

Bachelor thesis deals with design of a shipping container that is used for the transport of radioactive substances from nuclear power plants at regional storage. In the first part is described the notion of radioactive waste, its origin and distribution. The following chapters deal with the design of a shipping container in terms of design, quality and safety. The theoretical part ends with an overview of the current status of the use of shipping containers in the Czech Republic. A model presents a calculation of the measurements carried out with two real sources of ionizing radiation and influence of various materials. Calculation chapter is focused on the calculation of activity and attenuation using a steel shield. All calculations are performed for a point emitter. A measurement made with stronger volume emitter is done to the orientation showing the effect of shielding material to absorb ionizing radiation.