Silicon carbide (SiC) is a wide-bandgap semiconductor that is widely used in power electronics, automotive industries, and aerospace applications due to its high thermal conductivity and breakdown field. This review examines both the fundamental physics and the practical applications of SiC. We analyze its major crystal structures (polytypes), specifically 4H-SiC, 6H-SiC, and 3C-SiC, and discuss how these structures affect electrical performance. The paper also covers new developments in SiC functional ceramics, metal-matrix nanocomposites, and quantum defects used for quantum information science. By analyzing research literature from 2006 to 2026, we show how the industry transitioned from basic crystal growth to 8-inch wafer manufacturing and automated defect classification using neural networks. Finally, this review discusses the main technical problems that still limit SiC devices, such as high interface trap density (Dit), high contact resistance in p-type doping, and bias temperature instability (BTI). By comparing theoretical material properties with real device performance, this paper identifies key research priorities for the next generation of semiconductor technology.

This article presents the gross contents and chemical fractionation of trace elements in bottom sediments of the lower Shagan River. Twenty samples were collected at ten cross-sections between the outlet of Atomic Lake and the confluence with the Irtysh River. The point-by-point profiles show element-specific spatial patterns rather than one common accumulation zone. Local maxima of Li, Al, Cr, La, Ce, and Mn occur mainly 66–96 km downstream from Atomic Lake; Ga and Ba are higher in the upper part of the surveyed reach, while U and Mo show multiple separated peaks. Six fractions were identified: water-soluble, exchangeable, weakly specifically sorbed, organic-bound, Fe–Mn oxide/hydroxide-bound, and residual. Most elements, except Ga, had gross contents below upper continental crust values. Less than 20% was extracted using H₂O, Ca (NO₃)₂, and NaOH combined, whereas more than 70% of many elements occurred in poorly soluble forms.

This article presents the results of a study of the spatial distribution and occurrence forms of trace elements in the bottom sediments of the Karabulak Stream, located within the Degelen Mountains of the Semipalatinsk Test Site. Bottom sediment samples were collected at 19 points along the main stream channel and its four tributaries. A sequential extraction method was used to determine the occurrence forms of chemical elements. This method allows for the isolation of water-soluble, exchangeable, weakly specifically sorbed, organic matter-bound, iron and manganese oxideand hydroxide-bound, and residual forms. Quantitative determination of elements was performed using ICP-MS and ICP-AES. It was established that the distribution of trace elements in the bottom sediments is characterized by significant spatial heterogeneity due to the hydrological characteristics of the stream and the anthropogenic impact of the former test site. Exceedances of Clarke values were detected for a number of elements, primarily uranium, beryllium, molybdenum, and cadmium. The highest concentrations of Be, Sr, and Cd were observed in the upper reaches of the stream, while Mo and U contents increased in the lower reaches. Uranium in the bottom sediments of the main channel was shown to be predominantly in a watersoluble form, indicating its high migration capacity and potential environmental hazard.

This paper presents the results of optimizing the operating modes for the formation of low-energy Kr, Xe, and He ion beams at the DC-60 accelerator complex intended for simulation of radiation damage in materials. The electron cyclotron resonance (ECR) source of highly charged ions was upgraded by replacing the DECRIS-3 source with the modernized DECRIS-3M. In addition, the operating parameters of the ECR ion source, beam injection, transport, and scanning systems were optimized. The charge-state distributions and beam intensities were investigated; optimal beam formation conditions were determined, and a uniform beam current density distribution over the target surface was achieved. The average beam current on the target increased from 45 to 77 μA for He2+ ions, from 13 to 26 μA for Kr15+ ions, and from 6 to 14 μA for Xe23+ ions, corresponding to increases by factors of 1.7, 2.0, and 2.3, respectively. The obtained results reduce the time required to achieve the desired ion fluence and improve the efficiency of radiation damage simulation experiments in materials.

This study systematically examines the influence of high-velocity oxygen-fuel (HVOF) spraying parameters, with particular emphasis on oxygen pressure, on the microstructure and tribological performance of Al65Cu20Fe15 coatings. The coatings were deposited at two oxygen pressures (3.0 and 3.5 bar), while all other spraying parameters remained constant. Microstructural characterization was performed using scanning electron microscopy (SEM) and energy-dispersive spectroscopy (EDS), and phase composition was analyzed to assess the proportion of quasi-crystalline and crystalline phases. Tribological behavior was assessed using a ball-on-disk sliding test with continuous friction coefficient recording. The results show that oxygen pressure significantly influences coating density, phase composition, and tribofilm formation. The coating deposited by spraying at an oxygen pressure of 3.5 bar demonstrated the most balanced characteristics, with a stable friction coefficient of 0.55–0.60 and consistent wear, which is explained by a higher proportion of the quasicrystalline phase and a homogeneous tribofilm. Thus, the analysis revealed that processing the samples at 3.5 bar oxygen pressure is the optimal process mode, ensuring the formation of a denser microstructure and improved tribological properties of the coating.

This study presents the analysis of the influence of the protective capsule material on the neutron-physical characteristics of fuel element irradiation during experiments conducted at the IGR research reactor. The calculations were performed using the MCNP6 code and the ENDF/B-VII nuclear data libraries. Different structural materials of protective capsules used in the testing of experimental fuel assemblies were considered. The dependences of energy deposition, spectral characteristics of the neutron field, and spatial distribution of neutron flux on the composition and wall thickness of the protective capsule were determined. It was found that the choice of capsule material has a quantitatively measurable effect on the irradiation conditions of the fuel elements, which must be taken into account when interpreting the results of reactor experiments. The obtained results provide a basis for substantiating design solutions and optimizing the irradiation conditions of fuel elements.

Beryllium-based intermetallic compounds are considered promising functional and structural materials for advanced nuclear systems due to their favorable neutronic, thermal and activation characteristics. In this work, neutron-induced activation in titanium and chromium beryllides (Be12Ti and Be12Cr) containing technological impurities was investigated under fission and fusion neutron environments. Experimental gamma-spectrometric measurements and Monte Carlo calculations were performed for specimens irradiated in the WWR-K research reactor. Agreement between calculated and measured specific activities for the dominant activation products Sc-46, Mn-54, Fe-59 and Cr-51 confirms the applicability of the neutronics approach. Neutron-induced gas production (He-4, He-3, T and Li-6) was additionally evaluated for an ITER-relevant D-T spectrum under fixed-fluence conditions. The results demonstrate pronounced spectrum-dependent differences in activation and transmutation behaviour and provide a basis for extrapolating fission-irradiation data to fusion-relevant conditions.

This study provides a comprehensive analysis of PFAS contamination in the environment. An analysis of published scientific papers has shown that PFAS are exceptionally resistant to chemical, biological, and photolytic degradation, exhibit significant mobility in water, and can be dispersed across long distances.

PFAS are known as «forever chemicals» with half-lives of thousands of years. PFAS contaminate surface water sources and can accumulate in soil and air.

Detecting and analyzing their concentrations in the environment is crucial due to their extremely prevalent presence in natural habitats, presenting risks to public health and the integrity of the ecosystem.

A review of literature sources revealed that no studies of this problem have been conducted in Kazakhstan. This paper revealed a complete lack of publications on PFAS studies. The materials presented on the websites of Kazakhstani news agencies merely reflect the results of research by foreign scientists studying PFAS in the environment and biomaterials, reflecting the global problem of PFAS contamination.

The prerequisites for this area of research are the lack of publications in Kazakhstan, the lack of PFAS monitoring, the lack of systematic studies, including foreign ones, as well as the lack of various methods for determining PFAS in environmental objects, and this requires close scientific attention and study.

The article discusses conceptual design solutions for the disposal of spent nuclear fuel (SNF) from the BN-350 reactor. It analyzes technologies for the final disposal of SNF without processing, including mine disposal sites and deep wells in solid rocks. The article also examines conceptual design solutions for an underground laboratory, the design features of underground complexes, the organization of tunneling operations, engineering infrastructure, and transportation and processing schemes for containers containing SNF. The main characteristics of above-ground and underground structures, the volume of mining operations, and the parameters of mine shafts and technological sites are presented. It is shown that the use of a multi-level system of engineering and geological barriers ensures long-term radiation safety and minimizes the risk of radionuclide migration into the biosphere.

The Shulbinsk Hydroelectric Power Plant (HPP) is a critical infrastructure facility with a high level of engineering responsibility, necessitating a detailed assessment of local seismic hazard. This study presents the results of instrumental seismological investigations conducted within the Shulbinsk HPP area using data acquired from five temporary observation sites (SB1–SB5). Spectral characteristics of ambient seismic noise were analyzed, site response was evaluated using the Horizontal-to-Vertical Spectral Ratio (HVSR) method, and the obtained results were compared with amplitude ratios derived from recordings of earthquakes and quarry blasts.

The results indicate significant seismic heterogeneity across the study area. The most pronounced local amplification of seismic ground motion was identified at the embankment dam site (station SB1), where the increment in seismic intensity reaches approximately 0.7–0.9 points on the MSK-64 scale. In contrast, no significant increase in seismic intensity was observed at the remaining observation sites. The identified differences are associated with local soil conditions and low Vs30 values within the embankment body. Based on the consistency between the HVSR results and waveform analyses of recorded seismic events, recommendations are provided regarding the implementation of continuous seismic monitoring of the dam condition.

The paper presents the results of computational neutron-physical modeling of irradiation devices ID-M and WF containing fuel from VVER-1000, APR-1400, and HPR-1000 reactors and placed within the central experimental channel of the IGR reactor. Using the MCNP code system, calculations of the uranium-water ratio, specific power generation distributions in fuel rods, and average specific power along the active fuel height were performed. An analysis of the influence of the design features of single-wall and double-wall irradiation devices on the neutron-physical characteristics of the fuel was carried out. It was established that the use of the double-wall ID-M irradiation device results in approximately a 45% reduction in the average specific power generation level compared to the single-wall WF device. Comparison of the calculated characteristics of the irradiation devices with the corresponding parameters of VVER-1000, APR-1400, and HPR-1000 reactors demonstrated the possibility of reproducing in the IGR reactor power generation levels characteristic of fuel operation in commercial power reactors. The obtained results can be applied to the preparation of in-reactor testing of advanced nuclear fuels, thermal regime assessment, and safety assurance of experimental investigations.

This paper presents the results of the first experimental tests of the ion cyclotron radio-frequency (RF) plasma heating system of the KTM tokamak with an equivalent plasma load. Measurements of the operating parameters of the RF generator and the antenna-feeder system were carried out under conditions approximating plasma operation. The generator circuits were tuned and matched to the load, and the generation characteristics as well as the conditions for stable RF power transmission to the load were investigated. Stable operating regimes of the system and the conditions ensuring stable RF power generation were determined. The test results confirm the functionality of the main components of the RF heating system and demonstrate the possibility of further testing with plasma in the KTM tokamak.

During the comprehensive analysis of the structural parameters of the studied mechanically activated ZrO₂ ceramics, the optimal temperature range for heat treatment was established, ensuring maximum structural homogeneity, a high degree of structural ordering and a minimum concentration of residual mechanical stresses. An analysis of structural changes in ceramics, carried out using X-ray diffraction and Raman spectroscopy methods, made it possible to establish that an increase in annealing temperature leads to partial relaxation of mechanically induced stresses and redistribution of oxygen vacancies. Moreover, in the entire range of annealing temperatures studied, no initialization of phase polymorphic transformation processes, characteristic of zirconium dioxide in the case of intense mechanical pressures or the presence of a large number of oxygen vacancies, is observed. Analysis of the data obtained showed that at annealing temperatures of 1000 – 1100 °C, the structure is dominated by complex defects associated with the presence of deformation residual stresses and areas of strong disorder that arose under mechanical impact. With an increase in the annealing temperature to 1200 – 1300 °C, an equally probable distribution of defects in the structure is observed, while at temperatures above 1400°C, there is a dominance of F+ centers and VO – vacancies, the growth in the concentration of which is associated with an increase in structural ordering due to partial relaxation of defects and the formation of oxygen vacancies.

In this paper, a literature review on the application and features of boronization in tokamak-type devices is presented, and a methodology for preparing the vacuum chamber of the KTM tokamak for plasma experiments using a carboranebased boronization system is substantiated. The technical implementation of the process under glow discharge conditions is described, including the design of the vapor delivery system with a heated receiver and the transport line on the KTM tokamak. A project of the diagnostic complex under development for real-time monitoring of the environment purity, combining mass spectrometry and optical monitoring of the boron emission line, is presented.

The paper presents the results of a study on the relationship between the prompt and delayed components of energy release in the core of the pulsed research reactor IGR at the cold state. Using the MCNP6 code, a series of high-precision prompt and delayed energy release calculations was performed, yielding detailed data on the spatial distribution of energy release over all columns and blocks of the core and reflector. The Spearman rank correlation coefficient, applied to quantify the relationship, exceeded 0.98 for all analyzed columns, indicating a monotonic statistical relationship between the components. Parameters of a power-law approximation were determined by the least-squares method in logarithmic coordinates for eight column types, with a coefficient of determination R² above 0.97 confirming the adequacy of the models. It is emphasized that the established correlation does not prove a cause-and-effect relationship, but reflects the joint influence of a single neutron field on the formation of both energy release components. Unlike the conventional approach requiring direct calculation of the delayed component, the developed reconstructive approach allows the delayed energy release to be estimated from the prompt component using the proposed approximating dependences. The results can be used to speed up neutronic calculations in multi-variant analysis of experimental configurations and in the development of coupled simulation methodologies for reactor studies.

Ceramic materials based on lithium metatitanate (Li₂TiO₃) modified with lithium niobate (LiNbO₃) in the concentration range of 0.05–0.25 M were studied. The

Ceramic materials based on lithium metatitanate (Li₂TiO₃) modified with lithium niobate (LiNbO3) in the concentration range of 0.05–0.25 M were studied. The synthesis was carried out by mechanical activation in a planetary mill at grinding speeds of 150…600 rpm with a step of 50 rpm, followed by thermal stabilization at 700 °C for 5 hours. The objective of the work was to determine the relationship between the dopant concentration, the energy of mechanical processing and the structural and mechanical properties of the obtained ceramics.

The phase composition and structural parameters were studied by X-ray diffraction, and the morphological features of the ceramics were studied using scanning electron microscopy. The formation of a two-phase system, including the monoclinic Li₂TiO₃ phase and the rhombohedral LiNbO₃ phase, can be seen. The increase in the dopant content occurs simultaneously with changes in the parameters of the crystal lattice and a decrease in the size of the coherent scattering regions. SEM analysis showed pronounced changes in the morphology of ceramics upon the addition of LiNbO₃, depending on the dopant concentration. Increasing the mechanical activation rate to 600 rpm and increasing the alloying additive concentration to 0.25 M lead to the creation of a fine-grained composite microstructure, where an improvement in the strength characteristics is observed compared to the unalloyed material.

The obtained data show that the combination of changing the LiNbO₃ content and mechanical activation parameters is one of the most effective tools for controlling the phases and strength of lithium-containing ceramic materials, which opens up enormous opportunities for optimization in high-temperature energy applications.

This review systematizes and critically summarizes current knowledge of microcrystalline cellulose as a multifunctional material with considerable potential for property tailoring. Particular attention is given to the diversity of cellulose feedstocks, ranging from conventional sources such as wood and cotton to alternative agro-industrial residues, including rice husk, bagasse, straw, cocoa bean shells, and recycled textile materials. The analysis is structured around the relationship between feedstock architecture, isolation conditions, and the resulting functional properties of MCC. Major MCC production routes are examined in detail, including conventional acid hydrolysis, organosolv processing, HCl gasphase degradation, and hydrothermal treatment. The available evidence demonstrates that the characteristics of the initial lignocellulosic matrix, together with processing conditions, govern the degree of polymerization, crystallinity index, cellulose polymorphism, and particle morphology, thereby influencing the sorption behavior and chemical reactivity of the resulting material. Particular emphasis is placed on targeted chemical and physical modification strategies, including oxidation, esterification, and graft polymerization, which provide additional opportunities to tailor MCC performance. These approaches broaden its potential use in pharmaceutical formulations for direct compression, biomedical systems such as hydrogels and wound dressings, environmental sorbents, and advanced biocomposites. The scientific significance of this review lies in consolidating the transition from the conventional perception of MCC as a passive filler toward its consideration as an engineered functional precursor whose properties can be deliberately tailored for specific applications.

An assessment was made of the activity concentrations of natural and artificial radionuclides in the soil–vegetation cover of the arid zone of Kazakhstan along the 65th and 75th meridians. The mean activity concentrations in soils were 580.7 Bq/ kg for ⁴⁰K, 34.8 Bq/kg for ²³²Th, 23.0 Bq/kg for ²²⁶Ra, and 16.9 Bq/kg for ¹³⁷Cs. In plants, the mean activity concentrations calculated from the quantitatively determined values were 489.2 Bq/kg for ⁴⁰K, 2.5 Bq/kg for ²³²Th, 14.3 Bq/kg for ²²⁶Ra, and 1.2 Bq/kg for ¹³⁷Cs. The activity concentration of ²⁴¹Am could not be quantified. The highest variability in concentration ratio (CR) values was observed for ¹³⁷Cs, whereas relatively greater uptake by plants was observed for ⁴⁰K and ²²⁶Ra. The estimated absorbed dose rate to plants ranged from 1.6 to 8.9 µGy/day along the 65th meridian and from 3.7 to 15.0 µGy/day along the 75th meridian. These values were substantially below the levels at which radiation effects in reference species are expected. The results obtained can be used as baseline characteristics for radiation monitoring, assessment of radionuclide dynamics, and radiation dose burdens on biota, as well as for subsequent monitoring of the radiological status of the study area.

The article provides an overview of modern approaches to the management of liquid radioactive waste (LRW), their basic properties, classification, chemical and radionuclide composition are considered. The main problems of LRW processing related to the diversity of their composition, high salinity, the presence of organic impurities and the need for selective extraction of radionuclides have been analyzed. The existing technologies for the LRW treatment and conditioning have been analyzed, the international experience in the processing of liquid radioactive waste has been reviewed, and an assessment of the current state of LRW management in the Republic of Kazakhstan has been given. Special attention is paid to the issues of minimizing the volume of the generated waste, the introduction of technologies for deep treatment and radionuclide immobilization, and the analysis of the basic requirements for the composition, structure and physicomechanical properties of matrices used for conditioning radioactive waste.

The expediency of developing specialized regional LRW processing facilities and introducing a unified public management system in this area has been substantiated. It has been concluded that the integrated use of contemporary recycling technologies is necessary to reduce environmental risks, improve the safety of radioactive waste management and comply with international requirements.

The article summarizes data on radioactive contamination of the main environmental components of the Semipalatinsk Test Site (STS), including soil and vegetation cover, wildlife, surface waters, atmospheric air, and snow cover. The occurrence and distribution patterns of ³H, ⁹⁰Sr, ¹³⁷Cs, ²⁴¹Am, and ^239+240Pu, as well as the main mechanisms of their transfer among ecosystem components, are considered. The contamination of the territory is characterized by pronounced spatial heterogeneity, with the highest radionuclide levels associated with the epicenters of surface nuclear tests, radioactive fallout traces, areas around borehole outlets, water-filled craters, and zones affected by contaminated watercourses. In soils, most of the ¹³⁷Cs, ²⁴¹Am, and ^239+240Pu remains concentrated in the upper horizons and is associated with the solid phase, whereas ⁹⁰Sr exhibits the greatest vertical mobility. Radionuclide accumulation in plants and animals is determined by the contamination characteristics of their habitats, radionuclide properties, and species-specific biological characteristics. The highest levels of contamination in surface aquatic ecosystems are observed in artificial water bodies, bottom sediments, and watercourses at the Degelen site. The release of radionuclides into the atmosphere is associated with the transfer of ³H from contaminated waters and soil moisture, as well as with the resuspension and atmospheric transport of soil particles. The results demonstrate that present-day radioactive contamination of the STS is predominantly localized and is determined by the types of nuclear tests conducted and the subsequent redistribution of radionuclides in the environment.

The mass-energy distributions of fission fragments are formed by a large number of macroscopic and microscopic quantum effects associated with both charged liquid droplet effects and the formation of various nuclear shells in nascent fragments. Additionally, the final distribution is influenced by the excitation energy of the compound nucleus and the introduced angular momentum. All of this poses a challenge in analyzing experimental data for the presence/absence of various shell effects. This is particularly true for deformed nuclear shells, which, compared to spherical shells, have a significantly lower energy advantage for formation and, consequently, a smaller mass contribution. Therefore, the choice of analysis technique significantly influences the obtained result. To demonstrate this, we analyze the mass-energy distributions of fission fragments of the compound nucleus ²⁴¹Am produced in the ²⁴⁰Pu(p,f) reaction at an incident proton energy of 10 MeV using two methods. The first method is an earlier development based on the Broza model and takes into account the SL, S1, S2, and S3 fission modes, using a large number of fit parameters. The second method is a modification of the first, developed specifically to identify the influence of deformed nuclear shells with small contributions. Its advantages include a significant reduction in the number of fit parameters, which increases its sensitivity. The second method makes it possible to identify the yields of individual Z50 and N82 shells and separate them from the deformed Z52 and N84 nuclear shells, despite their similar mass yields.

An economic and legal model is developed to support management decisions on implementing an artificial intelligence (AI)-based advisory system for predictive diagnostics of rotating equipment at a nuclear power plant (NPP). The model links functional boundaries, data governance, independent validation, computer security, human oversight and change management requirements with life-cycle costs and investment indicators. An integrated realized-performance coefficient is proposed to account for model quality, equipment coverage, data availability and personnel use of recommendations. The assessment is performed for a hypothetical water-water energetic reactor unit rated at 1200 MWe (VVER-1200) in constant 2026 prices. In the baseline scenario, the project’s net present value (NPV) is USD 2.648 million, its internal rate of return (IRR) is 29.33%, and the discounted payback period is 4.90 years. The break-even realized-performance coefficient is 43.32%. The reduction in the levelized cost of electricity (LCOE) is USD 0.075/MWh and should be interpreted as a localised operational effect rather than a radical improvement in NPP competitiveness. A staged implementation approach is justified, with scaling allowed only after technical, legal, and economic criteria have been confirmed using pilotoperation data.

The paper presents a methodology for modeling the dynamics of volumetric fuel distribution based on the coupling of thermal-hydraulic and neutronic calculations. An algorithm was developed for the automated conversion of CFD simulation results into an MCNP computational model. The methodology makes it possible to account for changes in geometry, phase composition, and spatial distribution of fuel and structural materials during fuel degradation and melting processes. To achieve this, software was developed for processing thermal-hydraulic calculation data, generating computational lattices of various types, implementing an angular duplication algorithm, and automatically creating input files for neutronic calculations. Unlike the conventional approach, which relies on the development of a set of separate neutronic models corresponding to fixed stages of fuel degradation, the proposed methodology enables power distribution calculations for any state of the experimental device obtained from thermal-hydraulic simulations. Verification of the developed neutronic model of the test facility containing fuel within the reactor model of the IGR reactor was performed. The obtained results can be used for computational support of experiments investigating nuclear fuel degradation and melting processes, as well as for the development of coupled thermal-hydraulic and neutronic modeling methodologies for reactor research applications.

As part of the development of an experimental method for evaluating the accumulation and retention of hydrogen ions to address materials science problems related to thermonuclear fusion, titanium beryllide (Be₁₂Ti) samples produced in Kazakhstan were irradiated with high-energy deuterium ions. The choice of material is justified by existing concepts of fusion facilities, in which Be₁₂Ti is proposed for use as a first-wall material, for example, in JA DEMO. The investigated samples were irradiated with 14 MeV deuterium ions under two irradiation modes differing in irradiation time, particle flux density, and total fluence. To study the mechanisms of gas accumulation and release in the material, the irradiated Be₁₂Ti samples were examined by thermal desorption spectroscopy. The Be₁₂Ti sample exposed to a deuterium flux for a longer time at a relatively lower particle flux density demonstrated significantly higher accumulation of D⁺ ions. At the same time, the sample irradiated for a shorter time but with a high-density flux resulted in significantly lower gas accumulation. The results show that the high-energy deuterium ion irradiation technique can be used as an experimental approach for evaluating hydrogen accumulation and retention in materials for fusion facilities.

The K, L, and M X-ray yield cross sections were measured for elements from Ti to Bi excited by accelerated beams of 94.4 MeV 59Co12+ ions. The results were compared with the predictions of the ECPSSR and PWBA theories, calculated using the ISICS11 program. The obtained data show that the overall decrease in the K-shell X-ray yield cross section with increasing atomic number of the target is accompanied by an increase over the range from Z2 = 22 to Z2 ≈ 41, with a maximum at Z2 ≈ 29. This phenomenon can be explained by the fact that near-symmetric interactions allow electrons to move between the orbitals of colliding atoms through the resulting molecular orbitals. Consequently, the X-ray production cross section for a given chemical element can be selectively maximized by selecting the irradiation mode – the energy and type of the incident ion – during PIXE analysis. Based on the shifts and broadening of X-ray lines in the obtained spectra, fluorescence yields and K-shell ionization cross sections were calculated for elements from titanium to molybdenum, modified for multiple ionization. The results show that the differences between fluorescence yields accounting for multiple ionization and single-vacancy fluorescence yields do not exceed 35%. Consequently, the observed deviations of experimental data from theoretical ones cannot be explained solely by multiple ionization without invoking effects associated with interorbital electron transitions.