Influence of corrosion of the first circuit elements on the distribution of sediments in the circulation tract of the SMR 160 reactor

Authors

DOI:

https://doi.org/10.15587/2706-5448.2025.326512

Keywords:

modular reactor, water-chemical regime, corrosion, sediment, austenitic steel, zirconium

Abstract

The object of research is the circulation path of a water-water small modular reactor. The work is aimed at assessing the influence of corrosion intensity on the formation of sediments on the surfaces of the first circuit of the SMR 160 reactor module. The analysis of the circuit structure was performed, the intensity of corrosion destruction and the intensity of sediments on the local sections of the circuit are evaluated. The circulation circuit of vertical architecture, the movement of the coolant in which excites thermal pressure, created by heating in the core and cooling in the steam generator.

The methodology is based on the principle of material balance of the transition of corrosion products into the coolant and their sediment on the circuit surface. To estimate the speed of corrosion the results of complex studies conducted at stations in normal operation and on the physical models of sections of the first circuit in the laboratory were used. Estimation of the speed of sediments is performed according to the ratios that take into account the impact of the concentration of the sedimented substance in the coolant, the thermal load of the site and the consumption of the coolant.

The calculations showed that the main source of iron oxides in the circuit is the surface of the steam generator, causing the average value of their concentration in the final areas, and zirconium oxides come from the surface of the core and retain the concentration close to the average along the entire tract.

The research results showed that the high corrosion stability of the structural materials of the circuit significantly limits the transition and accumulation of corrosion products in the coolant. In turn, low concentrations of corrosion products in the coolant restrain the formation of their sediments on the surfaces of the core and steam generator. The values of the surface density of sediments and their average thickness are estimated.

Analysis of corrosion processes of structural materials and the distribution of their sediments in the circuit allow to predict the level of radiation contamination and to plan the service life of the system.

The presented technique allows to evaluate the effectiveness of the water -chemical regime used.

Author Biographies

Igor Kozlov, Odesа Polytechnic National University

Doctor of Technical Sciences, Professor

Department of Nuclear Power Plants

Vyacheslav Kovalchuk, Odesа Polytechnic National University

PhD, Associate Professor

Department of Nuclear Power Plants

Denys Stepura, Kyiv National Economic University named after Vadym Hetman

PhD Student

Department of Management

Maksym Lysak, Odesа Polytechnic National University

PhD Student

Department of Nuclear Power Plants

Viacheslav Miliev, Odesа Polytechnic National University

PhD Student

Department of Nuclear Power Plants

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Influence of corrosion of the first circuit elements on the distribution of sediments in the circulation tract of the SMR 160 reactor

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Published

2025-04-15

How to Cite

Kozlov, I., Kovalchuk, V., Stepura, D., Lysak, M., & Miliev, V. (2025). Influence of corrosion of the first circuit elements on the distribution of sediments in the circulation tract of the SMR 160 reactor. Technology Audit and Production Reserves, 2(1(82), 57–62. https://doi.org/10.15587/2706-5448.2025.326512

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Section

Technology and System of Power Supply