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EN
The paper is of a review character and in historical terms, it contains an overview of research on polonium from the time of its discovery in 1898 (125 years ago) to the present time. The article contains a description of the state of knowledge about the chemistry of polonium, taking into account its physicochemical properties, as well as methods of its production and the radioactivity of its isotopes, as well as its current scientific and industrial applications. The issue of strong radiotoxicity of polonium and the dangers associated with research on it, as well as numerous example of diseases and death from its absorption into the human body, are described in detail. Despite the passage of 125 years since the discovery of polonium, it still fascinates researchers with its mysteries that have not been fully understood, revealed and explained. The sources of this peculiarity should be sought in the fact that although it is classified as a metal, it also has non-metallic properties and can form a number of different chemical compounds. Several chemical compounds of polonium have been tested, which are very easy to get into the human body, where it causes terrible havoc. Alpha particles emitted from decay of 210Po can cause damage to proteins and DNA that load to cell death or such changes in the body that consequently initiate the development of cancer. So you could say that polonium not only has a rich past, but also has an undeniably interesting future.
2
Content available remote Transmutation: reducing the storage time of spent fuel
EN
Transmutation can reduce the storage time of spent fuel. Efficient transmutation requires a high flux of neutrons and can therefore be done only in nuclear reactors. The article shows the concepts of different solutions of transmutation in nuclear reactors. Knowledge of transmutation is supplemented by information on spent fuel and its radiotoxicity.
EN
This paper presents research on radionuclide transport from generic geological repository for the RBMK-1500 SNF of 2.8 235U initial enrichment (with Er absorber) and average burn-up of ~ 29 MWd/kgU. Radionuclide transport analysis was focused on the engineered barrier system (EBS) and performed taking into account possible differences in the data on the initial size of a canister defect, defect enlargement time and radionuclide release start time. For the numerical simulations, computer code AMBER (UK) was used. The analysis of radionuclide transport regularities demonstrates that the release from the EBS is the most intensive after the defect enlargement. Most relevant radionuclides were identified based on the mass transfer analysis complemented by the analysis of radiotoxicity flux. The results showed that, depending on the differences of the initial defect size, defect enlargement time and release start time, the peak flux from the EBS may vary by a factor of 2 (for 129I) and 1.5 (for 226Ra) for RBMK-1500 SNF.
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