Effect of Corrosion of the Fuel Rod Construction Materials on the Radiation Safety of Nuclear Power Plants with PWR
https://doi.org/10.21122/1029-7448-2020-63-1-89-98
Abstract
The article considers the general concept of corrosion in accordance with GOST 5272–68 “Metal Corrosion”, the classification of the corrosion process, the stages of corrosion as energy function of the flow path of the corrosion process, the main indicators of the corrosion process. According to the forecasts of the International Monetary Fund and Focus Economics, the amount of funds that will be spent on counteracting corrosion and its consequences in selected industrialized countries has been estimated. The growth of funds invested in the counteracting the effects of metal corrosion in the Russian Federation for 2016–2019 is presented in the form of a diagram. The substantiation of the use of zirconium as a structural material for the shell of fuel rods has been fulfilled. The values of the thermal neutron absorption cross sections for various elements serving as structural elements for the core of a nuclear reactor are presented. Factors influencing the choice of alloying elements and their percentage in various alloys (Zr-2, Zr-4, ZIRLO™, M5®), which are the special development that reduce the corrosion rate, are also considered. The composition and mechanical properties of E110 and E635 alloys, which were used as materials for the fuel rods shell in the core of WWER-1200 reactors at the Belarusian NPP, are considered as well. The behavior of zirconium alloys E110 and E635 in the core is analyzed. The main factors that make a significant contribution to the corrosion process in actual operating conditions of zirconium alloys as fuel rods shell have been identified. The existing methods of preliminary special processing of fuel rods shells stored in the air for a long time before their receipt for assembly are presented. The structure of the oxide on the shells of alloys E110 and E635 oxidized in an autoclave is demonstrated.
About the Authors
V. V. KravchenkoBelarus
Address for correspondence: Kravchenko Vladimir V. – Belаrusian National Technical University, 65/2 Nezavisimosty Ave., 220013, Minsk, Republic of Belarus. Tel.: +375 17 293-91-45 tes_bntu.@tut.by
S. D. Tsygankova
Belarus
Minsk
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Review
For citations:
Kravchenko V.V., Tsygankova S.D. Effect of Corrosion of the Fuel Rod Construction Materials on the Radiation Safety of Nuclear Power Plants with PWR. ENERGETIKA. Proceedings of CIS higher education institutions and power engineering associations. 2020;63(1):89-98. (In Russ.) https://doi.org/10.21122/1029-7448-2020-63-1-89-98