Isolation Of Radioactive Waste Research Articles

Correlating shale geochemistry with metal sorption: influence of kaolinite content

ABSTRACT Argillaceous rocks constituting clay fractions are potential host rock candidates for isolation of radioactive waste in underground repositories. The present study aims at characterization of two argillaceous rocks (shales) from different geological settings (surface and subsurface localities) and investigation of their cesium (Cs) sorption behaviour. The shales were characterized using various analytical techniques to evaluate the textural attributes, mineralogical constituents and surface properties. The major mineralogical constituent of the surface and subsurface shale was quartz (62%) and kaolinite (56%), respectively. The abundance of smectite and illite in both the shales was comparable. Fluorescence and UV-Vis spectra confirmed the presence of polyaromatic hydrocarbons (PAHs) in the subsurface shale. The subsurface shale demonstrated higher Cs retention (17 mg g−1) than the surface shale (12 mg g−1) due to higher kaolinite content. Surface analysis of the shale samples revealed involvement of ion exchange mechanism in Cs uptake. The agreement of experimental results with Freundlich sorption isotherm suggests the heterogenous nature of the shales with multiple sorption sites. The correlation of geochemistry (especially the kaolinite content) for both the shales with Cs sorption is clearly highlighted in the present studies. The present investigation implies the applicability of the studied shales for waste management applications.

Effect of Iron Chloride (II) on Bentonites under Hydrothermal Gradients: A Comparative Study between Sodium Bentonite and Calcium Bentonite

This study investigates the performance of two bentonite materials, specifically MX-80 (Na-bentonite) and FEBEX (Ca-Mg-Na-bentonite), employed as engineered barriers in deep geological disposal facilities for the isolation of high-level radioactive waste, contained in metallic canisters. Experiments conducted at the laboratory scale focused on the interaction of these bentonites with FeCl2 powder, used as a soluble iron source, to observe enhanced alteration of the bentonite. The experiments were carried out under a hydrothermal gradient. A dominant Na-Cl-SO4 saline solution was put in contact with the compacted bentonites from the top, while a constant temperature of 100 °C was maintained at the bottom using a heater in contact with the layer of FeCl2. The experimental cells were examined after six months of interaction. Various changes in the physical and chemical properties of the bentonites were observed. An increase in the water content, a reduction in the specific surface area and cation exchange capacity, changes in the distribution of aqueous species, and the formation of secondary minerals were observed. Reaction products formed at the bentonite interface with FeCl2, primarily comprising akaganeite, goethite, and hematite. The smectites showed evident structural modifications, with an enrichment in iron content, and a shift in the exchangeable ion distribution in the case of MX-80 bentonite. This work provides valuable insights into the complex interactions between bentonite barriers and materials that dissolve iron, serving as proxies for deep geological disposal environments and indicating the potential long-term behavior, taking into account higher concentrations of dissolved iron than those expected in a real repository.

Hybrid Sol–Gel and Spark Plasma Sintering to Produce Perovskite-like SrTiO3 Ceramics for Radioactive Waste Isolation

The paper presents a reliable technology combining sol–gel synthesis and spark plasma sintering (SPS) to obtain SrTiO3 perovskite-type ceramics with excellent physicomechanical properties and hydrolytic stability for the long-term retention of radioactive strontium radionuclides. The Pechini sol–gel method was used to synthesize SrTiO3 powder from Sr(NO3)2 and TiCl3 (15%) precursors. Ceramic matrix samples were fabricated by SPS in the temperature range of 900–1200 °C. The perovskite structure of the synthesized initial SrTiO3 powder was confirmed by X-ray diffraction and thermal analysis results. Scanning electron microscopy revealed agglomeration of the nanoparticles and a pronounced tendency for densification in the sintered compact with increasing sintering temperature. Chemical homogeneity of ceramics was confirmed by energy dispersive X-ray analysis. Physicochemical characteristic studies included density measurement results (3.11–4.80 g·cm−3), dilatometric dependencies, Vickers microhardness (20–900 HV), and hydrolytic stability (10−6–10−7 g·cm−2·day−2), exceeding GOST R 50926-96 and ISO 6961:1982 requirements for solid-state matrices. Ceramic sintered at 1200 °C demonstrated the lowest strontium leaching rate of 10−7 g/cm2·day, optimal for radioactive waste (RAW) isolation. The proposed approach can be used to fabricate mineral-like forms suitable for RAW handling.

Mineral Resources of the Russian Nuclear Industry and Isolation of Radioactive Waste

This article considers tasks needed to ensure sustainable development of the Russian nuclear industry, which are aimed for solving the problems of the initial and final stages of the nuclear fuel cycle, from reproduction of the uranium mineral-resource base to handling of liquid high-level waste of spent nuclear fuel reprocessing. The trends in the development of the mineral-resource complex are analyzed in connection with the projected growth of electricity generation at nuclear power plants. New approaches to the allocation and substantiation of prospecting areas based on the models of mineral-forming systems of uranium deposits using remote-sensing data, GIS modeling, and neural-network technologies are proposed on the example of the territory of southeastern Transbaikal within the framework of current prognostic and mineragenic studies. A detailed analysis of trends in solving the problems of the back end stage of the nuclear fuel cycle is carried out. The use of phosphate glass ceramics with monazite is proposed for isolation and subsequent disposal of the REE–actinide fraction of high-level waste.

Nanoscale Prediction of the Thermal, Mechanical, and Transport Properties of Hydrated Clay on 106- and 1015-Fold Larger Length and Time Scales.

Coupled thermal, hydraulic, mechanical, and chemical (THMC) processes, such as desiccation-driven cracking or chemically driven fluid flow, significantly impact the performance of composite materials formed by fluid-mediated nanoparticle assembly, including energy storage materials, ordinary Portland cement, bioinorganic nanocomposites, liquid crystals, and engineered clay barriers used in the isolation of hazardous wastes. These couplings are particularly important in the isolation of high-level radioactive waste (HLRW), where heat generated by radioactive decay can drive the temperature up to at least 373 K in the engineered barrier. Here, we use large-scale all-atom molecular dynamics simulations of hydrated smectite clay nanoparticle assemblages to predict the fundamental THMC properties of hydrated compacted clay over a wide range of temperatures (up to 373 K) and dry densities relevant to HLRW management. Equilibrium simulations of clay-water mixtures at different hydration levels are analyzed to quantify material properties, including thermal conductivity, heat capacity, thermal expansion, suction, water and ion self-diffusivity, and hydraulic conductivity. Predictions are validated against experimental results for the properties of compacted bentonite clay. Our results demonstrate the feasibility of using atomistic-level simulations of assemblages of clay nanoparticles on scales of tens of nanometers and nanoseconds to infer the properties of compacted bentonite on scales of centimeters and days, a direct upscaling over 6 orders of magnitude in space and 15 orders of magnitude in time.

Molecular dynamics simulation of thermal, hydraulic, and mechanical properties of bentonite clay at 298 to 373 K

Bentonite, a fine-grained geologic material rich in smectite clay, is considered for use in the isolation of high-level radioactive waste (HLRW) because of its low hydraulic permeability, high swelling pressure, and geochemical stability. A complicating factor in this application is that heat released by nuclear waste can trigger complex coupled thermal-hydraulic-mechanical-chemical (THMC) phenomena within the barrier. Prediction of these phenomena using large-scale simulators, which typically examine problems on scales of 10−2 to 104 m, is inhibited by insufficient knowledge of the material properties of bentonite and their dependence on temperature. Here, these properties were evaluated using replica-exchange molecular dynamics (REMD) simulations of a clay assemblage containing 27 Na-smectite nanoparticles with full atomistic-level resolution solvated using 187,131 water molecules. The simulations yielded predictions of heat capacity, thermal conductivity, thermal expansivity, hydraulic conductivity, and water and ion diffusivity at temperatures of 298 to 373 K. Results showed that temperature modulates the capacity of clay barriers to transfer heat, fluids, and chemical species to different degrees. Material properties of hydrated smectite predicted on scales of tens of nanometers and nanoseconds were consistent with the properties of bentonite measured on scales of centimeters and days.

Мониторинг напряженно-деформированного состояния массива горных пород при подземном захоронении жидких радиоактивных отходов

Ensuring reliable isolation of nuclear industry radioactive waste is determined by the technology of their injection, as well as the geological conditions of the environment where the disposal is carried out. In order to confirm the localization of liquid radioactive waste within the established forecast boundaries and confirm the technically sound condition of underground structures, work is being carried out to monitor the state of the subsoil and underground structures. The obtained results of monitoring the state of the subsoil and underground structures are used as input data for verification of models developed and used to justify the long-term safety of models and, if necessary, optimization of disposal regimes. The purpose of the geophysical studies described in the article was to assess the response of the geological environment to a change in the operation of an injection well. The work was carried out by the method of the natural pulsed electromagnetic field of the Earth, which was used for these purposes for the first time. The results of assessing the change in the stress-strain state of rocks in response to changes in reservoir pressure are presented. The conducted studies have shown the high prospects of the method for geotechnological monitoring of deep disposal sites for nuclear industry waste. The paper proposes new criteria for assessing the stress-strain state of rocks.

INFLUENCE OF ORIENTATION OF ACTIVATING TECTONIC FAULTS ON SAFETY OF A SYSTEM OF ISOLATION OF RADIOACTIVE WASTE

Methods of mathematical modeling were used for estimating an influence of tectonic faults activation of safety of a facility for final isolation of high-level radioactive waste at the site Yeniseiskiy (Krasnoyarsk region) by methods of mathematical modeling. A 3–D model of radionuclides transport by groundwater was considered taking into account a heterogeneity of rock permeability. Faults of different orientation were considered. We showed that a formation of new near-meridional faults or an activation of ancient ones did not exert a substantial influence on velocity of radioactive pollution propagation in underground medium. Near-latitudinal faults can affect the radionuclides to a more extent. We considered a possibility to confine this influence due to a technogeneous decrease of rock permeability within a relatively short interval of the fault zone.

The Influence of the Orientation of Activated Tectonic Faults on the Safety of a Radioactive Waste Isolation System

The Influence of the Orientation of Activated Tectonic Faults on the Safety of a Radioactive Waste Isolation System

Pragmatic Validation of Numerical Models Used for the Assessment of Radioactive Waste Repositories: A Perspective

The safety case for a radioactive waste repository relies heavily on results obtained by numerical models that assess the long-term performance of the engineered and natural barrier systems. Given that important engineering and public policy decisions are based on these models, it is essential that we critically evaluate their abilities and limitations, and thus justify the level of confidence we have in the inferences drawn from the modeling. In this article, we discuss some of the issues surrounding the modeler’s attempts to test, corroborate, confirm, and verify numerical models—a process sometimes referred to as model validation. This wide-ranging topic is approached by first examining its deep roots in the philosophy of science and hypothesis testing. However, the application of these principles to radioactive waste isolation calls for a more pragmatic approach, which has the narrower goal of corroborating site-specific models and their usefulness for a specific purpose. We focus on the practical aspects of validating hydrogeological models that are used to understand the evolution of the repository system. We will make the case that the responsible use of numerical models requires a sufficient understanding of the quality and robustness of the simulation results, with direct implications for how these results need to be interpreted, and how they can (or cannot) be used in support of important policy decisions.

Bentonite–Concrete Interactions in Engineered Barrier Systems during the Isolation of Radioactive Waste Based on the Results of Short-Term Laboratory Experiments

Bentonite clays have unique properties that determine their use as the main component of engineered barrier systems (EBS) for the isolation of radioactive waste. At present, the Russian Federation is elaborating the concept of deep geological disposal of radioactive waste in crystalline rocks of the Yeniseisky site, where bentonite clays play an important role in ensuring the safety of the repository for a long period of time. This work demonstrates the first results of short-term laboratory experiments (1 and 3 months) on the thermochemical interaction of bentonite and concrete in the presence of synthetic water at an elevated temperature. These experiments will help predict the effect of EBS materials on montmorillonite. Bentonite from the 10th Khutor deposit (Russia) and Portland cement were used in the experiments. At the first stage of the experiments, solutions were obtained after leaching the concrete with a synthetic groundwater solution for 1 month at 90 °C. At the second stage, the interactions of the obtained solutions with bentonite at 90 °C were studied. As a result of the experiments, the processes of concrete leaching were revealed, which changed the composition and acidity (an increase in the pH from 6.1 to 12.1) of the synthetic water and led to an increase in the porosity of the material in contact with the solution. However, no dissolution of montmorillonite was observed, and the changes were quite small. The research results show the high stability of bentonite from the 10th Khutor deposit under model conditions, which was confirmed by modeling. Thus, we can say that at pH ≈ 12 and at elevated temperatures, montmorillonite retains a stable structure for a long time, which is important for ensuring the safety of disposal in general.

Dynamic Activity Index for Feature Engineering of Geodynamic Data for Safe Underground Isolation of High-Level Radioactive Waste

In this study, we developed a new approach for feature engineering in geosciences. The main focus of this study was feature engineering based on the implementation of the dynamic activity index (MDAI) as a function of the anomaly of the spatial distribution of data, using systems and discrete mathematical analysis. The methodology for calculating MDAI by groups, geomorphological variability, the density of tectonic faults, stress-strain state, and magnetic field anomalies, is presented herein for a specific area. A detailed analysis of the correlation matrix of MDAI revealed weak correlations between the development features. This showed that the considered properties of the geological environment are independent sets and can be used in the analysis of its geodynamic stability. As a result, it was found that most of the territory where high-level radioactive waste (HLRW) disposal is currently planned is in a relatively stable zone.

Geodynamic interpretation of modern geodynamic Movements in the southern part of the Yenisei Ridge (in application to the problems of underground isolation of radioactive waste)

The results of geodynamic interpretation of the results of GNSS observations of presentday movements and modeling of the stress-strain state of the upper part of the Earth’s crust in the area of the construction of an underground research laboratory to substantiate the safety of disposal of high-level long-lived radioactive waste in granite-gneiss rocks of the Nizhne-Kansk massif are presented. The kinematic model of the area made it possible to assess the directions of block movements of large structural blocks. The greatest movement gradients were noted in the west, between the underground research laboratory site and the contact between the Siberian Platform and the West Siberian Plate along the Atamanovsky Fault. Local zones of stress concentration have been identified, in which destruction of the rock mass in the near-contour zone of underground workings is most likely. Analysis of models and results of GNSS observations showed that the structural-tectonic block, in which the construction of the underground research laboratory is planned, is in relatively calm geodynamic conditions. Present-day movements determine the regime of sublatitudinal compression in azimuth close to 100–1100 at the underground research laboratory construction site. A systematic analysis of geological and geophysical data made it possible to obtain new knowledge about the kinematics and stress-strain state of the rock mass in the southern part of the Yenisei Ridge, necessary to ensure the geoecological safety of isolation of high-level radioactive waste in the granite-gneiss rocks of the Nizhne-Kansk massif. This work was funded by the Russian Science Foundation (project No. 18-17-00241).

Improving the rheological properties of alkaline-activated geopolymers using water-free fluids

Geopolymer systems are quite successfully used in such operations as industrial and civil construction, production of fire - resistant concrete, isolation and disposal of radioactive waste, etc. The oil and gas industry was no exception. They are one of the most promising alternatives to Portland cement in insulation operations. They allow achieving sufficiently high performances of well construction strength, corrosion resistance, and in some compositions these parameters significantly exceed those of Portland cement. In recent years, a significant amount of research has been carried out aimed at the development of geo polymer compositions for cementing oil and gas wells, which showed that these systems have strength characteristics comparable to Portland cement, low permeability, resistance to drilling mud and reservoir conditions, and the ability to self-repair. However, despite all the advantages of Geo polymer systems, their most significant disadvantage is poor regulation of rheological properties. Geo polymers (GP) with low ash content do not provide the proper rheological characteristics for the use in insulation operations. Low values of pumpability of solutions are still a serious restriction for wide practical implementation. The use of geopolymer solutions with the correct selection of the compositional composition capable of demonstrating significant improvements in strength and rheological parameters as a result of mixing with anhydrous drilling fluids is a very promising solution to this problem. The paper presents the results of research on the additives of non-aqueous fluids such as oil- based and synthetic-based drilling fluids and inverted emulsion drilling fluids on rheology of geo polymers. The obtained results allow stating that the rheological parameters of geo polymer compositions improve up to comparable values with Portland cement, which considerably extends the range of application of these solutions to use in operations of primary, squeeze cementing and well workover.

SEM-EDX study of bentonite alteration under the influence of cement alkaline solutions

Bentonite is a key barrier for the isolation of high-level radioactive waste within Deep Geological Repository. However, bentonite may be altered by contact with cementitious materials and their alkaline pore fluids. This study offers an extensive morphological and semi-quantitative characterization of the bentonite surface exposed to three types of alkaline pore fluids released by different cement-based materials. The bentonite surfaces were studied using a thorough scanning electron microscopy exploration and analysed using an energy-dispersive X-ray detector (SEM-EDX). In addition, statistical, element mappings, X-ray diffraction and infrared spectroscopy analyses were performed. The aim was to have a picture of the morphological and chemical alterations of bentonite at very early stages in accordance with the integrated approach necessary to address bentonite stability in the long-term. As a consequence of the reactivity, two types of morphologies stood out in the matrix of bentonite: platelets and coatings-like crusts characterized by their high Mg and Ca content. These alterations presented a different scope depending on the type of alkaline pore solution involved and suggested the precipitation of authigenic magnesium silicate hydrates (M-S-H) and/or trioctahedral clay minerals and Ca‑carbonates. The knowledge of the performance of bentonite subjected to these alkaline solutions can help in the evaluation of the most suitable cement-based materials to be used next to bentonite.

Swelling Pressure and Permeability of Compacted Bentonite from 10th Khutor Deposit (Russia)

Bentonites from the 10th Khutor deposit (Republic of Khakassia, Russia) are considered a potential buffer material for isolation of radioactive waste in the crystalline rocks of Yeniseyskiy site (Krasnoyarskiy region). This study presents the results of a series of permeameter experiments with bentonite compacted to dry densities of 1.4, 1.6, and 1.8 g/cm3, saturated and permeated by the artificial groundwater from Yeniseyskiy Site. Permeation was conducted at hydraulic gradients of 180–80,000 m/m to simulate potential hydraulic conditions in the early post-closure phase of a deep geological repository (DGR). The respective swelling pressures of 0.8 ± 0.3, 2.2 ± 0.6, and 6.3 ± 0.3 MPa and permeabilities of (27 ± 15) × 10−20, (3.4 ± 0.8) × 10−20, and (0.96 ± 0.26) × 10−20 m2 were observed for the hydraulic gradient of 2000 m/m, which is recommended for the determination of undisturbed swelling pressures and permeabilities in permeameter experiments. Upon incremental increases in the hydraulic gradient, swelling pressures at all densities and permeability at the density of 1.8 g/cm3 remained unchanged, whereas permeabilities at 1.4 and 1.6 g/cm3 decreased overall by a factor of approximately 5 and 1.7, respectively. Seepage-induced consolidation and/or reorganisation of bentonite microstructure are considered possible reasons for these decreases.

Investigation of the insulating properties of the Cherkasy deposit clays for the creation of underlying screens of radioactive waste at the ‘Vector’ site

The lack of scientifically substantiated requirements, comprehensively developed and approved in a prescribed manner, for the usage of clays as a barrier material poses risks for the safe disposal of radioactive waste in facilities at the ‘Vector’ site for the period of their operation and closure. The bentonite clay from Ukraine’s largest Cherkasy deposit of bentonite and palygorskite clays is considered the most durable as the main component of the insulating (underlying) screens of radioactive waste disposal facilities. The main properties and compositional features of the Cherkasy natural bentonite clay (Dashukovskaya site, layer II) and its variety such as alkaline earth bentonite (activated soda bentonite), which provide isolation of radioactive waste in disposal, are considered. It is shown that the Cherkasy field has good waterproofing and barrier properties, including a high sorption capacity with respect to 90Sr and 137Cs, which is one of the main characteristics that ensure the safe disposal of radioactive waste. The alkaline earth bentonite absorbs 90Sr and 137Cs more efficiently than natural bentonite does. However, 90Sr is sorbed in larger quantities than 137Cs on both types of bentonite. With increasing time of interaction with an aqueous solution, both types demonstrate a redistribution of the mobile (exchangeable) and immobile (non-replaceable) forms of radionuclides. The contribution of the stationary form that does not participate in migration processes also increases. A comprehensive analysis of the bentonite clays of the Cherkasy deposit was carried out, taking into account the significance of recoverable reserves and the potential for improving the technical and economic parameters of clays. Thus, the Cherkasy bentonite clays can be recommended as an additional anti-migration engineering barrier for ground/near-surface facilities for the disposal of radioactive waste. When choosing the type of bentonite clay for use as a barrier in a radioactive waste disposal facility, one could take into account the data published in the article, but the question of applying the bentonite clays of the Cherkasy deposit to ensure the safe disposal of radioactive waste remains to be further studied.

Sorption of 90Sr and 137Cs on clays used to build safety barriers in radioactive waste storage facilities

The purpose of the work was to investigate the sorptive capacity of natural clay samples with respect to 90Sr and 137Cs to assess the possibility of using these as components of protective barriers at radioactive waste isolation facilities. Bentonite clays of the Zyryanskoye and Desyaty Khutor deposits and high-melting clay of the Kampanovskoye deposit were selected for the investigation. The capacity of clays for sorption through ionic exchange is characterized by the value of the cation exchange capacity (CEC). In the process of sorption experiments, all of the test clays displayed a high rate of extracting strontium and cesium radionuclides from aqueous solutions. It was shown that the sorption of 90Sr is affected by the content of montmorillonite in the samples: bentonite clays absorb up to 98–99% of the initial radionuclide content in the solution, while about 80% of strontium is sorbed by high-melting clay. Cesium is practically fully sorbed by the tested samples and the degree of sorption amounts to over 99%, the highest value of the distribution coefficient having been recorded for the Kampanovskoye sample (Kd = 5.0×103 cm3/g). The method of sorbed radionuclides fixation on the clay samples were identified by selective desorption using the modified Tessier methodology. It was shown that strontium ions are more mobile than ions of cesium up to 97% of which is retained by clays.

Сооружение комплекса переработки жидких радиоактивных отходов на белоярской АЭС

The tasks of ensuring the safety of the population and the environment during the operation of nuclear facilities are formulated. The necessity of the final isolation of conditioned radioactive waste generated as a result of production activities of enterprises and decommissioning of nuclear facilities is substantiated. Modern technologies for the safe management of liquid radioactive waste are considered. The experience of operation of liquid radioactive waste processing facilities at nuclear power plants is summarized. The capabilities of ion-selective sorption for the reduction of final radioactive product volume and its advantages in comparison with other methods of radioactive waste treatment are given. A description is given of a complex for liquid radioactive waste reprocessing which is being built at the Beloyarsk NPP in order to increase the reliability of operation and environmental protection. The methods chosen for the implementation of the liquid radioactive waste reprocessing program are listed as well as the processing lines forming the facility. The description is presented of a block-module facility of ion-selective treatment designed for the reprocessing of the residuum from the tanks of the liquid radioactive waste storages. Described is the block-module facility for the conditioning of the ion-exchange resins which were utilized for the purification of the residuum and discharged water from cobalt and cesium radionuclides and corrosion products of other transition metals, in order to gain the concentrated non-radioactive saline product and to pack it in the primary containers. A cementation facility is described which is designed for reprocessing of the sludge of radioactive waste from the tanks and vessels of the storages and the sludge of the ion-selective treatment facility by inclusion of radioactive waste into the cement blocks. The measures to prevent emissions into the environment during the operation of the liquid radioactive waste reprocessing complex are described. The data are presented on the systems of static and dynamic barriers preventing the ingress of radionuclides into the environment during the operation of the liquid radioactive waste reprocessing complex. The technical and managerial means are presented intended to protect the barriers and to preserve its efficiency in accordance with the general regulations of nuclear power plants safety ensuring.

Geodynamic aspects of high-level radioactive waste disposal: a case-study of Nizhnekansky massif

This article describes the methodological aspects and some results of the assessment and prediction of the geodynamic stability of the geological environment as applied to the problem of ensuring the safety of underground isolation of high-level radioactive waste (HLRW) in the geological formations of the Nizhnekansky massif, Krasnoyarsk Region. For this, the authors introduced a basic concept of the stability of the geological environment. Based on instrumental observations, mathematical models, system analysis of geospatial data, the ranking of structural tectonic blocks according to the degree of stability and the geodynamic zoning of the northern part of the Nizhnekansky massif were implemented. To assess the stability, the authors used geological data, a digital elevation model, the results of the interpretation of geophysical fields and geodetic observations. It is shown that the stability of the blocks differs significantly according to kinematic parameters. Geodetic observations based on GPS/GLONASS satellite systems, carried out in 2010-2019, made it possible to obtain for the first time information on the rates of horizontal movements of the lithosphere and their cyclicity for the region located in the zone of force interaction of the largest tectonic structures, namely, Siberian platform, West Siberian plate and the Altai-Sayan Orogen. The maximum speeds were recorded for points located in the zone of dynamic influence of the Muratovsky and Pravoberezhny faults. The energy concentration criteria as the fracturability characteristics of structural rock blocks are proposed for the stress–strain analysis of rock mass. To substantiate the long-term geodynamic safety of deep disposals of HLRW of the 1st and 2nd classes, the authors developed a program for the long-term observations of differentiated movements in the earth’s crust and seismic activity for 2021–2026 in an underground research laboratory. The study was carried out under the state contract between the Geophysical Center of the Russian Academy of Sciences and the Ministry of Science and Higher Education of the Russian Federation.