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dc.contributor.authorГапон, Ю.К.-
dc.contributor.authorKUSTOV, Maksym-
dc.contributor.authorKALUGIN, Volodumur-
dc.contributor.authorSAVCHENKO, Alexander-
dc.date.accessioned2021-11-25T08:30:55Z-
dc.date.available2021-11-25T08:30:55Z-
dc.date.issued2021-07-13-
dc.identifier.citationTrans Tech Publications Ltd, Switzerlandru_RU
dc.identifier.issn1662-9752-
dc.identifier.urihttp://repositsc.nuczu.edu.ua/handle/123456789/13827-
dc.descriptionAs of today, there are four nuclear power plants are operating in Ukraine, where operate 15 VVER type (water-water energetic reactor) units with total capacity of 13,880 MW. Over the past decade, the total annual production of electric power in Ukraine increased, the share of energy production at nuclear power plants increased as well. In other words, atomic power has turned into the main stabilizing factor of the country's energy system. All these facts as well as the analysis of the country's energy needs and capability to meet them is evidence of expedience and necessity of the atomic energetics development in Ukraine [1,2]. Choice of this exact way will correspond with the global trend as well. The main direction of efforts of the global atomic energy scientific community is ensuring the safety of nuclear power plants operation. One of the most relevant directions of ensuring the nuclear power plants operation safety is studying the fuel elements corrosion processes in order to solve the issue of their operating life increasing. The physical and chemical peculiarities of the fuel elements operation are of the holistic character and depend on the zirconium alloys chemical composition in the body of fuel elements, coolant temperature and chemical composition (water steam) and coolant hydrodynamic motion through the fuel elements components. Therefore, researching the kinetics and mechanisms of fuel elements corrosion is a relevant area of research.ru_RU
dc.description.abstractThe paper deals with experimental data regarding the effect of internal and external factors on the corrosion decay of Zr1Nb alloy fuel elements. Based on the analysis results, losses of zirconium that transfers to oxide or coolant as per the fuel element wall weight and thickness as well as economic losses from their corrosion decay have been theoretically calculated. To avoid a state-level emergency occurrence, an increase in the fuel element wall thickness up to 660 µm is proposed, which can increase the operating life under the conditions of trouble-free coolant mass transfer hydrodynamic mode.ru_RU
dc.language.isoenru_RU
dc.publisherTrans Tech Publications Ltd, Switzerlandru_RU
dc.relation.ispartofseriesVol. 1038;pp 108-115-
dc.subjectnuclear powerru_RU
dc.subjectfuel elements,ru_RU
dc.subjectcorrosion processesru_RU
dc.subjectzirconium alloyru_RU
dc.subjectemperatureru_RU
dc.subjectwater radiolysis productsru_RU
dc.titleStudying the Effect of Fuel Elements Structural Materials Corrosion on their Operating Liferu_RU
dc.typeArticleru_RU
Розташовується у зібраннях:Кафедра спеціальної хімії та хімічної технології

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