Radioactive Waste Disposal Facility Research Articles

Enhanced radioactive waste drum monitoring: A sensorized LoRa-based network for identification and integrity assessment

A reliable monitoring and oversight system is essential to guarantee the safe operation and eventual closure of radioactive waste disposal facilities. With recent technological advancements, there is now the capability to deploy distributed wireless sensor networks that are cost-effective and low in power consumption. Such networks are versatile, finding applications in several civil, environmental, and industrial sectors. This work presents a novel system and method for identifying and continuously monitoring the integrity of stored radioactive waste packages. The proposed approach, developed by the University of Pisa in the context of the H2020 European Project PREDIS, employs a network of wireless node devices, provided with solid-state micro-power radiation detectors tasked with the measurement of gamma-rays and thermal neutrons coming from within cemented waste drums. Collected data are automatically transmitted across the storage site via Long Range radio technology and forwarded to cloud-based or offline platforms, allowing for further visualization, data processing, and safe storage. The system highlights the feasibility of autonomously and passively gathering data from radioactive waste drums over extended distances (more than 250 m in non-line-of-sight conditions), decreasing the reliance on portable or automated scanning mechanisms. In line with its capability for autonomous, long-range data collection, the system satisfies the requirement for structural integrity, containment, and confinement of packaging throughout both interim and long-term disposal of radioactive wastes, thereby playing a key role in reinforcing the safe management of radioactive waste.

Effect of silver chloride deposition technique on modified bentonite operating properties for radioactive iodide-ions localization in geological disposal facility for radioactive waste

This work discusses the influence of the technique of silver chloride deposition (via one-stage or two-stage method) onto performance attributes of modified bentonite for iodine ions localization in radioactive waste repositories. It has been established that bentonite modified via both techniques in wide range of AgCl content has high sorption properties (more than 95%) towards iodide anions, the AgCl deposition method has little-to-no effect on sorption properties. Investigation by scanning electron microscopy and energy dispersive X-ray spectroscopy methods and studying of silver leaching in various media showed that two-stage technique yield more uniform AgCl distribution and significantly higher resistance of AgCl to leaching than one-stage technique. Therefore, as a component of bentonite engineered safety barrier in geological disposal facility for radioactive waste use of bentonite modified with two-stage technique is preferable.

Comparative Studies between Frequency Domain Analysis and Time Domain Analysis on Free-Field One-Dimensional Shear Wave Propagation

In Korea, the underground silo structure for low- and intermediate-level radioactive waste disposal facilities has been constructed and operated since 2014. Large-scale earthquakes occurred in 2016 and 2017, respectively, in Gyeongju and Pohang areas near the underground silo structures, and interest in the stability of the underground silo increased significantly. In this paper, one-dimensional free-field analyses have been carried out before the three-dimensional silo dynamic analyses subjected to earthquake loadings. As an additional study, a new form of the finite element equilibrium equation is derived in terms of relative motions, which is essentially the same equation expressed in terms of total motions where the base shear force is applied to the earthquake load. The accuracy of conventional finite element solutions is evaluated by directly comparing them with closed-form solutions by frequency domain analysis such as SHAKE91.

Basic Study on Applicability to Artificial Barriers for Radioactive Waste Disposal Facility for Various Zeolites

Artificial barriers are being considered for the burial disposal of low-level radioactive waste in Japan. The artificial barrier consists of i) a low permeable layer made of bentonite materials that suppresses migration of nuclides due to advection, and ii) a low diffusion layer that uses cementitious materials that suppresses migration of nuclides due to diffusion. In addition, as methods of disposing of radioactive waste generated by the accident at the Fukushima Daiichi Nuclear Power Station, controlled disposal and isolation-type disposal are being considered. We thought that it would be effective to add adsorption performance to the performance of suppressing migration of such radioactive substances. In this study, we designed and experimented on the adsorption performance of mortar mixed with various zeolites, which had never been examined. As evaluation methods, i) fluidity, ii) strength, iii) low diffusivity, and iv) distribution coefficient of cesium and iodine were obtained. Based on the results, we reexamined the composition and conducted experiments to examine the applicability to high-adsorption artificial barriers. As a result, it was confirmed that the mass transfer resistance tends to be low due to the zeolite being porous. It was also shown that the strength of mortar mixed with zeolite depends on the cement matrix. As a result of this research, the distribution coefficient of cesium in cementitious materials using zeolite with a high cation exchange capacity designed in this research is higher than that of cementitious materials for low-level radioactive waste disposal facilities currently in operation 1,500 times was obtained. On the other hand, we were able to discover the possibility of examining construction on a full-scale regarding fluidity and compressive strength. As a future task, it was found that it is necessary to investigate a more practical artificial barrier by increasing the strength and densification of the cement paste.

Clays of the Republic of Belarus as engineering barriers for disposal of radioactive waste

Тhe criteria for compliance with which the properties and characteristics of clays from industrially exploited deposits of the Republic of Belarus were assessed in order to determine the possibility of their further use as part of the underlying screen of the radioactive waste disposal facility (RWDF) of the Belarusian NPP are defined. The performed experimental analysis of clay samples from 12 deposits of the Republic of Belarus showed that clays from the “Gorodnoye” deposits of the Brest region and the “Markovskoye” deposits of the Gomel region have optimal quality indicators for use as part of the RWDF engineering barrier (underlying screen). It has been established that these clay samples have high sorption properties for 137Cs and 85Sr radionuclides. The values of the degree of sorption of 137Cs and 85Sr radionuclides from an aqueous solution for the above clay samples are about 99 %, and the values of the quantitative indicator of sorption the coefficient of distribution of radionuclides – are about 104 l/kg. Over time, the fixation of 137Cs on the studied clay samples increases; as part of the underlying RWDF screen, these clays will be an effective anti-migration barrier to prevent the migration of radionuclides into the environment in the event of depressurization of radioactive waste packages.

Numerical gas flow simulation performed to analyze advective gas flow in a compacted clay material

Burial of nuclear waste in a clay formation can result in the generation of significant amount of hydrogen and other gases due to corrosion of metallic materials under anoxic conditions, radioactive decay of waste, and radiolysis of water. If the rate of gas production exceeds the rate of gas diffusion within the clay porewater, formation and accumulations of a discrete gas phase will occur until the gas pressure becomes large enough to surpass the surrounding material gas-entry pressure; at that critical point occurrence of dilating and advective gas flow is expected [1]. Precompacted bentonite is suggested as a sealing material for the isolation of boreholes, disposal galleries, and deposition holes in a deep geological disposal facility for radioactive waste. Both formation of new porosity and the spread of dilatant pathways have been related to the advective flow of gas in bentonite [2]. Understanding of the processes and mechanisms involved is a key aspect when evaluating the impact of gas flow on repository design and construction of any future facility. A series of gas injection tests on compacted bentonite were carried out at the British Geological Survey within DECOVALEX-2023 (D-23) Task B: MAGIC and LASGIT. The project focuses on the development of new numerical techniques for the quantitative prediction of gas flow in repository systems.
 DECOVALEX-2023 Task B started with Modelling Advection of Gas In Clays (MAGIC). The planned approach of the task includes different stages, with an initial conceptual model development phase. In this work, the D-23 MAGIC has been studied based on the same methodology as previously applied in the work for DECOVALEX-2019 Task A - stage 1A (ENGINEER) using the same material properties and modelling strategy [3, 4]. Based on the actual dimensions of the sample, the 3D finite element model includes the geometry of the sample, the injection rod, the shape of the injection tip, the back pressure and the two filters associated to the location of the sensors. Hexahedral elements have been generated utilizing the CODE_BRIGHT software [5], and the random heterogeneity have been defined considering 3 different materials (M1-M2-M3). Layer-by-layer random permeability distribution was assumed (see Figure 1) applying 2/3–1/6–1/6 weighting for intrinsic permeabilities (ki) equal to 1×10-21, 1×10-20 and 1×10-19 m2, for materials M1, M2 and M3, respectively, as well as incorporating different embedded fracture parameters.
 LASGIT (LArge Scale Gas Injection Tests modelling) is a full-scale demonstration experiment operated by SKB at the Äspö Hard Rock Laboratory Hard Rock Laboratory at a depth of 420 m [6]. The 3D finite element model geometry is generated according to the real dimension of the test. Tests measurements included pressure and rate of gas inflow, gas outflow volume and pore pressure observed at various points of the sample. The gas test 1 of the LASGIT experiment is modeled in this study using a multiphase flow in porous media approach with the aim of facilitating the creation of favorable gas migration routes assuming permeability heterogeneity (Figure 1(b)), the same strategy as the MAGIC random permeability distribution outlined above. In this case, a coupled hydro-gas 3D FEM numerical model has been developed by the UPC/Andra research team to simulate the gas flow tests using the computer software CODE_BRIGHT, including initial permeability heterogeneity throughout the model. The numerical formulation also includes embedded fractures. The proposed model has been able to reproduce satisfactorily the observed behavior of the test measurements.

Modelling gas fracturing experiments in saturated clay using zero-thickness interface elements

The injection of gas in a liquid-saturated clay-rich material may lead to the formation of narrow channels or fractures created by the mechanical action of gas pressure. However, the complexity of the mechanical and transport properties of clays, combined with the high compressibility of gases, makes it challenging to understand and address this phenomenon. Gas fracturing can occur in a range of engineered processes, for instance the stimulation of sensitive hydro-carbon reservoirs [1], carbon dioxide injection and storage in subsurface reservoirs [2], pneumatic fracturing for enhanced remediation of contaminated soils [3], or gas transport through natural and engineered clay barriers in geological disposal facilities for radioactive waste [4]. Despite the multiple environmental and economic implications associated with gas fracturing it remains difficult to predict and control due to the lack of fundamental scientific insight.
 One of the most challenging aspects of understanding gas-driven cracking in clays is the difficulty in visualising the crack formation in real time. In recent years, a new experimental setup has been proposed by the British Geological Survey, which makes it possible to induce and observe the formation of “two dimensional” cracks in clay-rich low-permeability materials by the injection of gas or water [5,6]. In this setup, a thin layer (~1mm) of clay paste is compressed between a 110 mm diameter sight glass and a steel plate, while it is held laterally in place by a ring filter (Figure 1). Then, gas is injected at the centre of the lower platen at a controlled volumetric rate while the cracks induced are registered by a camera through the sight glass.
 In order to aid the interpretation of the results obtained with this new device, the authors have carried out a series of numerical simulations performed with a finite element approach recently published [7], and compared them to experimental data. The model uses a fully coupled Pneumo-Hydro-Mechanical (PHM) formulation in 2D, and is implemented in the code LAGAMINE [8]. Two different types of finite elements are used: continuum and interface elements. Continuum elements are used to represent the mechanical and flow processes in the bulk clay material and interface elements are used to represent cracks. Interface elements are introduced a priori in between the continuum elements in order to provide potential cracking paths. The model parameters are such that, as long as the interface elements remain closed, they do not have any significant effect on the response of the model.
 These simulations required two additional numerical developments. First, since the model is 2D (plane strain), the tangential, frictional stresses developed at top (clay-glass interface) and bottom (clay-steel interface) were introduced as a body force, using an elastoplastic formulation in terms of the in-plane displacements and the out-of-plane stress. Second, a mixed boundary condition was implemented to make it possible to impose a given volumetric gas injection rate as in the experiments.
 The simulations show that the model proposed can reproduce the experimental results, providing valuable insights into the factors controlling the onset and propagation of the gas fractures (Figure 1). These insights have the potential to enhance the performance and safety of projects involving gas fracturing processes

Impact of far-field glacially-induced stresses on fault stability in the eastern Paris Basin

Stable Continental Regions (SCR) feature very low seismicity levels, but historical seismicity reveals that these areas can experience large damaging earthquakes of magnitude up to Mw ≈ 7, on faults that were previously undocumented or thought to be stable. Glacial Isostatic Adjustment (GIA) is commonly considered as a factor of SCR deformation and stress perturbations that can trigger fault failure in formerly glaciated areas. Studies suggest that fault reactivation due to GIA may not only be restricted to glaciated areas, but could also occur in their periphery, several hundreds of kilometers away from the former glaciations. In this study, we model GIA associated to the Alpine, Massif Central, Celtic and Scandinavian glaciations from the last glacial cycle, in order to estimate the impact of this process on fault stability in the eastern Paris Basin, an area featuring very low strain rates and seismic activity, but of particular interest due to the proposed construction of a radioactive waste disposal facility. Our computations predict stress perturbations far (hundreds of kilometers away) from the ice loads, of similar amplitude to those in areas where fault reactivation has been observed (1–8 MPa at LGM, 0.8–2 MPa at present-day in our study area). We also show that the interaction between several GIA systems can impact the timing of maximum fault destabilization in a different way than common models considering only a single ice load. The computed far-field glacially-induced stress perturbations remain small compared to ambient crustal stresses, but they are large enough to potentially destabilize faults close to Andersonian geometries, with known faults in the eastern Paris Basin meeting these criteria, mainly in the Marne and Saint-Martin-de-Bossenay fault systems. Yet, there is no known evidence of Quaternary fault activity in the Paris Basin, and discrepancies between the localization of potentially unstable faults due to GIA and seismically active areas in northern France suggests that other processes must be at play.

International Atomic Energy Agency (IAEA) support for the management of site investigations for radioactive waste disposal facilities

Abstract. Providing safe, secure and environmentally acceptable radioactive waste disposal is a national responsibility that requires a long-term commitment, adequate resources and the involvement of multiple stakeholders. The choice of a particular disposal concept and its detailed design will depend on several factors, such as the properties of the waste inventory to be disposed of, national circumstances and strategic preferences. A concept is likely to evolve iteratively as one or more sites are investigated and the repository design is refined to reflect local conditions. In this context, the International Atomic Energy Agency (IAEA) recently published technical guidance on the management of site investigations for radioactive waste repositories. A key objective of the publication Management of Site Investigations for Radioactive Waste Disposal Facilities (IAEA, 2023) is to ensure that site investigation efforts in Member states have firm foundations based on a clear understanding of data and information requirements. The publication was developed to reflect the experiences and knowledge from a range of disposal programmes, and it is intended to support initiation of well-planned and focused site investigations in Member states with a need to develop and site radioactive waste disposal facilities. A siting process is intended to result in the identification of a suitable location for any nuclear installation, including a deep geological repository, and ultimately to receive authorisation to construct and operate the facility. To achieve this objective, it will be necessary to ensure that the combination of site properties and engineered barrier properties provides requisite levels of safety for the inventory under consideration (IAEA, 2015). The siting process and associated site investigations for a radioactive waste disposal facility follow a stepwise process, irrespective of whether the early stages of siting start with investigating and screening the national territory or whether the iterative investigation process starts with a more focused approach, e.g. volunteer sites, sites with already well-known characteristics, sites with existing nuclear facilities or similar ones (IAEA, 2023). Site investigations should follow a graded approach in an iterative manner, reflecting a phased approach to decision-making and the development of disposal facilities (IAEA, 2011). At each stage in the siting process the disposal system is to be evaluated based on the data and information available at that time. Following an assessment, a gap analysis comparing requirements to knowledge about the site would identify process model and data uncertainties affecting confidence in the implementation of the disposal concept at the site. Furthermore, the IAEA also recently launched a project to develop guidance reflecting good practices in Member states' programmes for establishing site selection criteria and applying a decision-making framework as part of a siting process.

Site-specific characterisation of hydrogeological parameters for low-level solid radioactive waste disposal facility at Tarapur, India

Site-specific characterisation of hydrogeological parameters for low-level solid radioactive waste disposal facility at Tarapur, India

Methodology to compare alternative design options for radioactive waste disposal facilities under the principle of ALARA based on probabilistic approach with Bayesian inference.

In the process of optimisation of radiological protection in long-term radioactive waste management, design options for disposal facilities are assessed from the viewpoint of practical reduction in radiation dose to as low as reasonably achievable (ALARA). In this paper, a probabilistic approach is introduced to evaluate differences in dose distributions between alternative facility designs using the Bayesian inference technique. It is demonstrated by a series of parametric calculations for hypothetic disposal system designs that an additional dose from an disposal facility could be sufficiently reduced from the viewpoint of dose reduction under the ALARA principle if the design option for a disposal facility whose 95th percentile of dose distribution is lower than the target dose of 0.1mSv/y is provided. Reducing uncertainties of the distribution of dose from disposal options is also an important aspect for the practical reduction in radiation dose to which members of the public are exposed.

Microstructural investigation into the damage behaviour of MX80 bentonite pellet under wetting/drying path using Mercury Intrusion Porosimetry (MIP) and Micro-Computed Tomography (μCT)

MX80 bentonite pellet has been considered as a promising sealing/backfilling material in geological disposal facilities for high-level and intermediate-level radioactive wastes. As the sealing/backfilling material which is subjected to hydration by pore water or vapour from host rock can be damaged by wetting-induced cracking, it is essential to clarify the suction effect on the damage behaviour of the material. In this study, a combined Mercury Intrusion Porosimetry/Micro-Computed Tomography (MIP/μCT) method was applied to investigate the microstructural damage of the MX80 bentonite cylinder-shaped 32-mm pellets equilibrated under suctions s from 113 to 1.5 MPa for wetting and from 113 to 262 MPa for drying. The enlarged pore size distribution (PSD) curves by MIP/μCT revealed an insignificant drying-induced closure of cracks, as opposed to massively developed wetting-induced cracks, with the size of the largest cracks reaching several millimetres. This is confirmed by the μCT observation. Indeed, the μCT images showed a negligible effect of drying on cracking, contrary to the effect of wetting characterised by significant cracking from the marginal area to the central part of pellet, indicating significant damage of pellet by wetting. Additionally, only horizontal cracks were identified at s ≥ 82 MPa. Vertical cracks emerged and propagated only at s ≤ 57 MPa, together with further expanding of horizontal cracks, due to the preferentially horizontal orientation of clay particles resulting from the one-dimensional compaction in the pellet fabrication. A damage coefficient D was defined as the ratio of the volume of macro-pores to the total volume of pellet. D increased slightly upon drying from suction 113 to 262 MPa and significantly upon wetting from suction 113 to 3.2 MPa, but kept almost unchanged when wetting furthered from suction 3.2 to 1.5 MPa because the clogging of macro-pores by the exfoliation effect slowed down the cracking rate.

Leachability of lead, cadmium, and antimony in cement solidified waste in a silo-type radioactive waste disposal facility environment

The waste acceptance criteria for heavy metals in mixed waste should be developed by reflecting the leaching behaviors that could highly depend on the repository design and environment surrounding the waste. The current standards widely used to evaluate the leaching characteristics of heavy metals would not be appropriate for the silo-type repository since they are developed for landfills, which are more common than a silo-type repository. This research aimed to explore the leaching behaviors of cementitious waste with Pb, Cd, and Sb metallic and oxide powders in an environment simulating a silo-type radioactive waste repository. The Toxicity Characteristic Leaching Procedure (TCLP) and the ANS 16.1 standard were employed with standard and two modified solutions: concrete-saturated deionized and underground water. The compositions and elemental distribution of leachates and specimens were analyzed using an inductively coupled plasma optical emission spectrometer (ICP-OES) and energy-dispersive X-ray spectroscopy combined with scanning electron microscopy (SEM-EDS). Lead and antimony demonstrated high leaching levels in the modified leaching solutions, while cadmium exhibited minimal leaching behavior and remained mainly within the cement matrix. The results emphasize the significance of understanding heavy metals' leaching behavior in the repository's geochemical environment, which could accelerate or mitigate the reaction.

Effects of low doses of gamma radiation on the human body

The purpose of this study was to investigate the incidence of additional cases of malignant neoplasms (MN) in a comparative aspect between the settlement living next to a radioactive waste disposal facility (RWDF) and the indicators of an environmentally clean area of the same territorial unit (region). Evaluation of radiation situation on the residential territory adjacent to the RAW disposal facility in settlement 1, and in settlement 2 (comparison settlement), as well as interpretation of the obtained data was performed in strict compliance with the requirements of regulatory documents specifying requirements to the research object. When performing measurements, the methodology described in the regulatory documents establishing these rules was used: MU 2.6.1.2398-08 "Radiation Monitoring and Sanitary-Epidemiological Assessment of Land Plots for Construction of Residential Buildings, Public and Industrial Buildings with Respect to Radiation Safety". The residents of the settlement 1 were found to be exposed to 3.7 mSv/year, i.e. 54.2% more than the average whole-year exposure dose received by the residents of the settlement 1 from natural background (2.4 mSv/year), which results in excessive risk of MHC development compared to the ecologically clean region. This indicates that excessive risk of MNS can occur even in conditions of radiation background within the considered safe dose of not more than 5 mSv/year. However, this risk is much lower than that from high doses of radiation. This makes it urgent to search for solutions that would allow implementation of the recommendations of the Chief State Sanitary Doctor of Russia regarding reduction of total radiation dose to 1 mSv per year or to develop measures allowing to neutralize harmful effects of radiation exposure on the human body.

CHENILLE: Coupled Behavior Understanding of Faults: from the Laboratory to the Field

Abstract. The understanding of coupled thermo-hydro-mechanical behaviour of fault zones or in naturally fractured reservoirs is essential both for fundamental and applied sciences and in particular for the safety assessment of radioactive waste disposal facilities. The overall objective of the CHENILLE project is to better understand the physical processes resulting from thermal and hydraulic loading in a small fault zone in a highly consolidated shale formation. Consequently, a thermally controlled in-situ fluid injection experiment is intended to be performed on a strike-slip fault zone outcropping at the Tournemire/France Underground Research Laboratory (URL). A heating system has been installed around the injection area to enable a precise and controlled incremental increase of the thermal load. Different monitoring systems are designed to measure the seismic and aseismic deformation induced either by thermal and/or by hydraulic loading. The seismic monitoring system is composed of Acoustic Emission (AE) and broadband seismic sensors enabling monitoring of seismic fracturing processes down to sub-decimetre scale as well as slow deformation processes. Furthermore, we are about to install an injection chamber allowing to perform a controlled gaz injection test. The injection borehole will also be partly equipped with fiber optics in order to measure temperature in a distributed manner in the borehole. Time-lapse active seismic surveys are scheduled for before and after the experiment to image the structural network but also to detect the appearance of new structures triggered from the hydro-thermal pressurization of the fault as well as eventual changes in the velocity field.

Application of Cement-Based Materials as a Component of an Engineered Barrier System at Geological Disposal Facilities for Radioactive Waste—A Review

Over the past several decades, the international community has been actively engaged in developing a safe method for isolating spent nuclear fuel, high and intermediate level radioactive wase of different degrees of heat generation in deep geological formations on the basis of regulatory requirements existing in each individual country (for example, in the Russian Federation-NP-055-14). Such a storage facility should be equipped with an engineered safety barrier system that combines a range of materials capable of ensuring the safe localization of environmentally and health-threatening nuclear power generation industry and the nuclear industry waste products, in particular. On the basis of the international experience discussed in this article on the design and operation of such facilities, the most universal material in terms of the functions performed as a component of the engineered barrier system is cement and the cement-based product mixed with various components—concrete. Furthermore, due to the possible mutual influence of buffer materials and their transformation over time at interfaces, this work considers the impact of cement-based barriers on other components of engineered barrier systems, the information on which has been accumulated as a result of both analytical laboratory tests and in situ radioactive waste disposal facilities under construction.

Обоснование выбора площадки размещения пунктов захоронения радиоактивных отходов с использованием многокритериального анализа

The paper proposes an approach supporting the decision-making on the site selection for radioactive waste disposal facilities (RWDFs) based on expert judgments involving multi-criteria decision analysis (MCDA). It suggests the analytic hierarchy process seen as a most widely used MCDA method for its mathematical implementation. The paper demonstrates the benefits of the proposed approach: structured procedure enabling the selection of most suitable RWDF sites, as well as transparent and convincing reasoning behind the site selection process.

Telemetric information system for geoecological monitoring of the state of subsoil and underground structures of deep disposal facilities for liquid radioactive waste

Telemetric information system for geoecological monitoring of the state of subsoil and underground structures of deep disposal facilities for liquid radioactive waste

Рациональное использование лицензионных участков недр при обращении с жидкими радиоактивными отходами при их захоронении в геологических формациях

The paper considers the structure of a deep disposal facility for liquid radioactive waste, the diagram of liquid radioactive waste spread within the mining allotment, and technical solutions enabling filtration flow redistribution through the use of barrage injection and extraction wells or observation and backup wells to provide long-term safe operation of the facility.

Месторождения урана под экраном многолетнемерзлых пород как природная аналогия геологического хранилища на период предстоящего похолодания климата

The article evaluates the conditions at the site proposed for a geological radioactive waste (RW) disposal facility (DGR) considering the scenario of the upcoming climate cooling. The evaluation is based on the analogy method with the comparison made against modern conditions explored at uranium deposits confined to the permafrost zone. The analogy is based on modern hydrogeological data from the Transbaikalia deposits explored using the underground borehole leaching method. This method yields no significant disturbance of the groundwater flow patterns. The study provides comparative analysis of climatic, geological and hydrogeological characteristics of the DGR siting area in the Krasnoyarsk Territory and those of uranium deposits in Transbaikalia. The limitations of this method have been validated. The paper highlights the main characteristics of groundwater flows in sub-permafrost aquifers. The results obtained may prove to be helpful in the development of models demonstrating radionuclide transport from the DGR developed at the Yeniseiskiy site.