Method of Quality Control of Nuclear Reactor Element Tightness to Improve Environmental Safety

Eduard Khomiak, Roman Trishch, Joanicjusz Nazarko (), Miloslav Novotný and Vladislavas Petraškevičius
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Eduard Khomiak: Department of Mechatronics and Electrical Engineering, Ukraine National Aerospace University “Kharkiv Aviation Institute”, 17 Vadym Manko Street, Khar, 61070 Kharkiv, Ukraine
Roman Trishch: Department of Mechatronics and Electrical Engineering, Ukraine National Aerospace University “Kharkiv Aviation Institute”, 17 Vadym Manko Street, Khar, 61070 Kharkiv, Ukraine
Joanicjusz Nazarko: Faculty of Engineering Management, Bialystok University of Technology, Wiejska 45A, 15-351 Bialystok, Poland
Miloslav Novotný: Faculty of Civil Engineering, Institute of Building Structures, Brno University of Technology, 602 00 Brno, Czech Republic
Vladislavas Petraškevičius: Department of Economic Engineering, Faculty of Business Management, Vilnius Gediminas Technical University, LT-10223 Vilnius, Lithuania

Energies, 2025, vol. 18, issue 9, 1-14

Abstract: Low carbon dioxide (CO 2 ) emissions make nuclear energy crucial in decarbonizing the economy. In this context, nuclear safety, and especially the operation of nuclear power plants, remains a critical issue. This article presents a new fractal cluster method of control that improves the quality of assessing fuel element cladding integrity, which is critical for nuclear and environmental safety. The proposed non-destructive testing method allows for detecting defects on the inner and outer cladding surfaces without removing the elements from the nuclear reactor, which ensures prompt response and prevention of radiation leakage. Studies have shown that the fractal dimension of the cladding surface, which varies from 2.1 to 2.5, indicates significant heterogeneity caused by mechanical damage or corrosion, which can affect its integrity. The density analysis of defect clusters allows quantifying their concentration per unit area, which is an important indicator for assessing the risks associated with the operation of nuclear facilities. The data obtained are used to assess the impact of defects on the vessel’s integrity and, in turn, on nuclear safety. The monitoring results are transmitted in real time to the operator’s automated workstation, allowing for timely decision making to prevent radioactive releases and improve environmental safety. The proposed method is a promising tool for ensuring reliable quality control of the fuel element cladding condition and improving nuclear and environmental safety. While the study is based on VVER-1000 reactor data, the flexibility of the proposed methodology suggests its potential applicability to other reactor types, opening avenues for broader implementation in diverse nuclear systems.

Keywords: nuclear safety; environmental safety; quality control; fuel element; radiation release prevention; nuclear reactor elements; non-destructive testing (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2025
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