This study investigates photocatalytic cells based on cocatalyst-loaded SrTiO₃:Al and nano-SiO₂ as a porous binder, immobilized on frosted glass. Comprehensive analysis confirmed the successful incorporation of aluminum into SrTiO₃, increasing oxygen vacancy concentration and enhancing charge transfer. The deposition of RhCr₂O₃ and CoOOH cocatalysts significantly improved photocatalytic activity, boosting hydrogen and oxygen evolution rates to 3.8401 and 1.6319 mmol g⁻¹ h⁻¹, respectively. The introduction of nano-SiO₂ increased hardness (0.23–0.25 GPa) and Young’s modulus (5.27–5.40 GPa), reinforcing structural integrity. The development of efficient photocatalytic panels requires a multifaceted strategy that considers chemical, mechanical, and optical properties together with stability, durability, and energy efficiency. Future research should focus on optimizing these key parameters to enhance system performance for industrial applications.

This article presents the results of studies of the degradation of the structure and mechanical properties of the core materials BN-350 fast neutron and research WWR-K reactors required to justify the service life extension of early-generation power and research reactors. Extending the service life of nuclear reactors is a modern problem, since most operating reactors are early-generation reactors that have exhausted their design lifespan. The possibility of extending the service life is largely determined by the condition of the structural materials of the nuclear facility, i.e., their residual resources must ensure safe operation of the reactor. For the SAV-1 alloy, the structural material of the WWR-K reactor, studies were conducted on witness samples which were in the active zone during its operation for 56 years. It was found that yield strength and tensile strength of the irradiated SAV-1 alloy decreased by 24–48%, and relative elongation decreased by ~2% compared to the unirradiated alloy. Inside the grains and along their boundaries, there were particles of secondary phases enriched with silicon, which is typical for aged aluminum alloys. For irradiated structural steels of power reactors, studied at 350–450 C, hardening and a damping nature of creep were revealed, caused by dispersion hardening and the Hall–Petch effect.

Research into the application of protective beryllide coatings in thermonuclear devices and high-temperature structures is currently of great interest. In thermonuclear devices, beryllides serve as an alternative to pure beryllium. Because beryllides exhibit high corrosion resistance and thermal stability, it was proposed to explore the possibility of using tantalum beryllide as protective coatings for high-temperature structural components. Such structures are used, among other things, in nuclear and thermonuclear facilities. Magnetron tests of tantalum beryllide coatings on stainless steel were conducted under high-temperature oxidation conditions. This article presents new experimental results on the high-temperature corrosion resistance of tantalum beryllide coatings. Coatings subjected to high-temperature oxidation were investigated using gravimetry, RBS analysis, X-ray diffractometry, and high-resolution scanning electron microscopy. The data obtained from the various methods are consistent, enabling a well-founded assessment of the coatings’ durability. It has been determined that, following the tests, the coating thickness decreases by more than a factor of two. A maximum Be diffusion depth of 400 nm into the substrate is achieved at a test temperature of 900 °C. The test results showed relatively low coating resistance under high-temperature oxidation conditions. However, under the test conditions, they contributed to a reduction in corrosion damage to the substrate surface. This makes it possible to classify tantalum beryllide as a promising protective coating for high-temperature materials.

Research into the application of protective titanium beryllide coatings in thermonuclear devices and high-temperature structures is currently of great interest. However, the harsh operating environments of thermonuclear devices impose severe thermal loads, causing rapid oxidation and degradation of structural materials like stainless steel. While titanium beryllide serves as a promising high-temperature alternative to pure beryllium, its long-term corrosion behavior and structural stability under extreme thermal conditions remain insufficiently understood. This paper presents the results of a study of titanium beryllide protective coatings under high-temperature corrosion testing conditions. Titanium beryllide coatings were applied to a stainless steel substrate using DC magnetron sputtering. Isothermal oxidation in air was used to determine the corrosion resistance of the coated steel. Test temperatures were 700, 900, and 1100 °C. Testing and subsequent studies of coating and substrate degradation demonstrated that titanium beryllide coatings effectively protect the substrate material from high-temperature oxidation. Moreover, the mechanism of coating structure transformation changes with increasing temperature. The interdiffusion of substrate and coating elements allows for an extended protective effect of the coatings.