Next Article in Journal
Modeling and Complex Characteristics of Urban Subway Co-Opetition Network: A Case Study of Wuhan
Next Article in Special Issue
On the Sustainable Utilization of Geopolymers for Safe Management of Radioactive Waste: A Review
Previous Article in Journal
Analysis of Systemic Risk Scenarios and Stabilization Effect of Monetary Policy under the COVID-19 Shock and Pharmaceutical Economic Recession
Previous Article in Special Issue
Recent Advances in Alternative Cementitious Materials for Nuclear Waste Immobilization: A Review
 
 
Font Type:
Arial Georgia Verdana
Font Size:
Aa Aa Aa
Line Spacing:
Column Width:
Background:
Article

Influence of Rock Structure on Migration of Radioactive Colloids from an Underground Repository of High-Level Radioactive Waste

by
Victor I. Malkovsky
,
Vladislav A. Petrov
,
Sergey V. Yudintsev
,
Michael I. Ojovan
* and
Valeri V. Poluektov
Institute of Geology of Ore Deposits, Petrography, Mineralogy, and Geochemistry Russian Academy of Sciences, Staromonetny Lane, 35, 119017 Moscow, Russia
*
Author to whom correspondence should be addressed.
Sustainability 2023, 15(1), 882; https://doi.org/10.3390/su15010882
Submission received: 29 November 2022 / Revised: 29 December 2022 / Accepted: 30 December 2022 / Published: 3 January 2023
(This article belongs to the Special Issue Nuclear Waste Management and Sustainability)

Abstract

:
Studies of leaching of vitrified simulated high-level radioactive waste (HLW) evidence that most of actinides or their simulators enter leaching water in a colloidal form. In this paper, we consider a mechanism of colloid-facilitated migration of radionuclides from an underground repository of HLW located at a depth of a few hundreds of meters in fractured crystalline rocks. The comparison between data of field and laboratory measurements showed that the bulk permeability of the rock massif in field tests is much greater than the permeability of rock samples in laboratory experiments due to an influence of a network of fractures in the rock massif. Our theoretical analysis presents evidence that this difference can take place even in a case when the network is not continuous, and the fractures are isolated with each other through a porous low-permeable matrix of the rock. Results of modelling revealed a possibility of mechanical retention of radionuclide-bearing colloid particles in the frame of rock during their underground migration.

1. Introduction

Observed climate changes and the necessity to reduce emission of greenhouse gases increases the significance of nuclear power engineering. Sustainable development of the atomic industry calls for a safe solution of high-level radioactive waste (HLW) management. The most effective and reliable approach to solving the problem at present is disposal of conditioned (solidified) HLW in underground repositories at a depth of several hundred meters [1,2,3]. Safety of such geological repositories is based on the multibarrier concept, which implies that both engineered and natural barriers provide for a reliable isolation of HLW in the repository from the biosphere. The engineered barriers include waste forms, canisters, and containers for solid HLW, backfill for holes in the repository where the canisters are disposed of, and repository construction units. The natural barrier is a rock massif between the loaded part of the repository and the biosphere [2,4]. The engineered barriers can degrade during the time period that is comparable with the half-life of many radionuclides from the HLW’s composition [5]. As a result, after an initial period, the rocks can be considered as the main isolation barrier protecting the biosphere from HLW. The main hazard of radionuclides ingress from HLW to the biosphere is caused by their transport by groundwater, which flows in rocks through systems of connected pore and fracture voids [6,7,8]. These systems are called flow channels, the scales of which are considered in [9]. Reliability of HLW isolation depends on the time of radionuclides migration from the loaded part of the repository to the biosphere. Concentration of radionuclides in groundwater decreases during their migration to the biosphere due to radioactive decay. If the concentration in the groundwater at its leakage to the earth surface (or to a water reservoir or a river net) is less than a maximum allowable level, the natural barrier is reliable, and the repository is safe [1]. Therefore, duration of radionuclides migration through the rocks and then the migration velocity is of paramount importance for the repository safety.
This paper analyses the process of radionuclide migration from underground repositories to the biosphere via colloid-facilitated transport of radionuclides by flowing groundwater accounting for the mechanical retention of colloidal radionuclide-bearing particles.
Continuum-scale modeling of groundwater flow in fractured rock with an explicit treatment of rock fracturing is used in many safety assessments of hazardous underground radiation objects. One of the first such models was proposed by Barenblatt et al. [10]. Development of this approach as applied to contaminant transport in fractured rocks was presented by J. Bear [6], I. Neretnieks [7], and C.-F. Tsang [11]. Reviews of methods for continuum-scale modeling flow in fractured rocks are provided in [12,13]. Most attention is paid to the influence of fractures that form a connected network. However, there is an option that the fractures do not form a linked structure even in a case when elevated permeability of the rock indicates directly a significant influence of rock fracturing. The fracture network channelizes the groundwater flow in this case, but the fractures can be disconnected, and parts of the groundwater streamlines between the fractures run through the rock matrix.
A substantial ecological hazard can be caused by a release of radionuclides from the underground repository of HLW and their transport from the repository to the biosphere. The groundwater can carry radionuclides as ions and colloid particles (radiocolloids). Since the radiocolloids can be much more mobile in the underground medium than the radionuclide ions they can represent the most hazardous form of radionuclides migration [8]. The intervals of the rock matrix between the disconnected fractures along the same streamlines of the groundwater can serve as filters for the particles of radionuclide-bearing colloids. Analysis of this option is the objective of this study.
We show that (i) even a system of disconnected fractures can cause a difference by a few orders of magnitude between bulk permeability of rock massif and permeability of the nonfractured rock matrix; (ii) analysis of permeability measurement at the site of potential federal repository of HLW indicates that fractures in the rock are, at least, partially disconnected; (iii) intervals between the disconnected fractures along the same streamlines of the groundwater can be effective filters retaining radionuclide-bearing colloids. Analysis of the influence of disconnected fractures on the bulk permeability of rocks is carried out by methods of computer modelling.

2. Colloid-Facilitated Transport of Radionuclides by Groundwater

As a result of sorption on walls of the flow channels, cations of many radionuclides should move at a velocity that is much less than velocity of the groundwater [14,15]. Let us denote velocities of any contaminant and the groundwater as V c and V f , respectively. As a first approximation, one can assume that sorption is reversible and satisfies the linear equation
C r = ρ K d C ,
where C r and C are mass fractions of the contaminant in the rock and in the groundwater, ρ is groundwater density, K d is a coefficient which characterizes sorption properties of the rock to the contaminant.
Then ratio between Vc and Vf satisfies the expression
V c / V f = 1 / 1 + ρ r K d / φ ,
where ρr is rock density and φ is rock porosity.
The higher sorption properties of the rocks to the contaminant ( K d ), the less is the ratio Vc/Vf. If sorption of radionuclides on the rocks is absent, the ratio Vc/Vf tends to 1, which is the maximum value of this ratio except of particular cases that are considered in [16,17,18,19,20]. However, results of radiation monitoring at the sites of significant radioactive pollution showed that values of Vc/Vf were much higher than it was predicted on the basis of sorption properties of the rocks to the radionuclides [16,17,18,19,20,21,22,23]. Similar result was obtained in laboratory experiments [24]. Elevated values of the radionuclide’s migration velocity as compared to its predicted values were explained by the assumption that groundwater carries radionuclides not only as a solute, but also in bound form as colloid particles (by definition, particles are called colloidal if their size ranges from 1 to 1000 nm), which are sorbed by the rocks to a lower extent than the radionuclide ions [25]. Colloid particles that carry radionuclides in groundwater are called radiocolloids. The colloids are subdivided into three main groups according to their origin: intrinsic colloids, primary colloids and pseudocolloids [26,27]. Intrinsic colloids consist of particles of colloid size that are composed to a significant extent of radioactive isotopes and their oxi- and hydroxides. Primary colloids represent colloid particles composed of leaching products of HLW vitreous form at its contact with groundwater. Pseudocolloids consist of colloid particles existing in the groundwater before contact with radioactive materials. At contact of the particles with polluted water radionuclides will be sorbed on these particles.
At present, immobilization of HLW on industrial scale is carried out using Al-P- or B-Si-glass [3,28,29]. Experiments on leaching of aged Na-Al-P-glass by water show that more than 95% of actinide simulators in the leaching products are attached to particles with diameter between 450 and 100 nm [30,31,32]. Thus, primary colloids represent more than 95% of actinide simulators’ ingress into the groundwater. Former studies have demonstrated that formation of two kinds of radioactive colloids: (1) primary—at hydrothermal alteration of vitreous waste forms and (2) pseudocolloids—at expense of initial colloids of waters or derived from eroded bentonite buffer are typical processes in the environment of underground HLW repository [17,18,19,20,21,22,23,24,25,33,34,35]. Therefore, one can expect that practically all actinides resulting from nuclear waste forms corrosion can be carried by the groundwater in highly mobile colloidal form, which will potentially decrease the safety of the repository [32]. However, the probability exists that diameters of the primary colloid particles can be larger than apertures of the filtration channels, and the coarsest fraction of primary colloids will be mechanically retained. Analysis of this possibility is the main subject of this study.

3. Influence of Rock Fracturing

It is known that the bulk permeability of crystalline rocks is usually higher by 1–3 orders of magnitude than the permeability of rock matrix, which is obtained in laboratory measurements on small (≅10−2 m in size) samples [36,37]. This is caused by the influence of fractures, the lengths of which are much larger than dimensions of interstitial voids and pores of the rock matrix. The latter focuses on the mainstream of the groundwater, which flows through the rock massif. Since they are much larger in size than rock samples used for laboratory measurement of permeability, laboratory measurements do not take into account the influence of fractures, and the permeability of small samples (i.e., permeability of the rock matrix) is much less than the bulk permeability of the massif. One can suppose in this case that mechanical retention of radiocolloid should be absent because the significant difference between bulk and sample permeabilities suggests that the fracture network and relatively large apertures of fractures are quite sufficient for free movement of radiocolloid particles along the fractures with the mainstream of the groundwater.
However, the elevated bulk permeability compared with the rock matrix permeability do only indicate on presence of fractures, although separate fractures can be disconnected and do not form a linked network through the rock massif.
Let us examine the influence of disconnected fractures on bulk permeability of rocks. We first consider a 2D cross-section of a fractured rock with porous matrix and chessboard ordering of the disconnected fractures directed along a mean flow of groundwater in the rock massif (Figure 1a) noting that the cross-section can be inclined in a general case.
Let us consider the groundwater flow in the recurrent cell G and introduce in it Cartesian coordinates as shown in Figure 1b.
The water flow in the porous matrix (outside the fractures) is governed by Darcy’s law [15]
v x = k m μ p x , v y = k m μ p y ,
where v x , v y are components of the Darcy’s velocity, km is permeability of the porous matrix, μ is dynamic viscosity of the groundwater, p = P + ρ g z ( x , y ) , P is pressure, ρ is groundwater density, g is acceleration due to gravity, z ( x , y ) is altitude of the point with coordinates x and y above any fixed horizontal plane. Since the cross-section is a plane, z ( x , y ) is a linear function. If the cross-section is horizontal, then p = P + c o n s t .
Since the groundwater is practically incompressible, components of the velocity satisfy the continuity equation in the form
v x x + v y y = 0 .
Hence, p satisfies the Laplace equation
2 p x 2 + 2 p y 2 = 0 .
We assume that the average velocity in cross-sections of fractures is governed by 1D Darcy’s equation [6]. Then, the flow in the fractures is governed by mass balance equations in the form
δ k f k m 2 p x 2 y = 0 = p y y = δ + 0 , 0 < x < L 1 or 2 L L 1 < x < 2 L ; δ k f k m 2 p x 2 y = H = p y y = H δ 0 , L L 1 < x < L + L 1 ,
where 2 δ is fracture aperture, 2 L 1 is fracture length, 2 L is length of the recurrent cell G.
As a result of mirror symmetry of the streamlines,
p y = 0 , y = 0 , L 1 < x < 2 L L 1 , p y = 0 , y = H , x < L L 1 or x > L + L 1 . ,
Let us denote pressures at x = 0 , 2 L as p0 and p1, respectively. It follows from the mirror symmetry of streamlines that p0 and p1 do not depend on y. Hence,
x = 0 , p = p 0 ; x = 2 L , p = p 1 .
Equalities (6)–(8) are boundary conditions for the Equation (5). The boundary problem (5)–(8) was solved numerically by finite differences method of successive over relaxation. Since the considered porous–fractured medium consists of recurrent cells G, we can express the bulk permeability of the medium on the basis of the obtained numerical solution as
k b u l k = μ H 2 L p 0 p 1 0 H v x d y .
Results of kbulk calculations can be approximated by the dimensionless expression
k b u l k k m = F ( h , l , M ) = h 2 F 1 ( h , l , M ) + 0.328 F 2 ( h , l , M ) h 2 + 0.328 ,
where
l = L L 1 , h = H L 1 , M = δ k f L 1 k m ,   F 1 = 1 4 l π h F M cos π 2 l + exp π ( M + 2.62 2 l , F 2 = 1 + h 2 M + 0.439 h 2 h 1.46 / ( l 1 ) 0.138 + 0.439 F M F l , F M = M / ( M + 2.62 ) , F l = exp ( l 1 ) 2 1 + ( l 1 ) 3.57
Comparison of k b u l k / k m obtained numerically and calculated by approximating Formula (10) is shown in Figure 2.
The chessboard ordering of fractures is of particular importance for estimation of the influence of disconnected fracturing on bulk permeability of rock massifs. Let us consider disconnected fractures of equal length and aperture, which are disposed with equal spacing in rows, and distances between neighboring rows are equal. An example of this type of fracturing is the considered case of chessboard ordering of fractures. Another example is a rectangle-cluster ordering of the fractures (Figure 3).
We show that chessboard ordering corresponds to an extremum in influence of such fracturing on bulk permeability of rocks. Let us enumerate fracture rows. In the case of chessboard ordering, middles of fractures in odd rows correspond to middles of intervals between fractures in even rows (Figure 4a).
Let us shift odd rows by a distance Δ along the row directions (Figure 4b). We denote the bulk permeability of obtained medium as k b u l k ( Δ ) . Then we consider shift of the odd rows from their initial position by a distance Δ in opposite direction, i.e., by − Δ (Figure 4c). Permeability of the medium in this case is k b u l k ( Δ ) . Boundary problem (5)–(8) is linear. This implies in particular that the value of bulk permeability does not change if direction of the mean flow becomes opposite. Therefore, k b u l k ( Δ ) = k b u l k ( Δ ) . Hence, k b u l k ( Δ ) is an even function, and
d k b u l k d Δ ( 0 ) = 0 .
Therefore, Δ = 0 (which corresponds to chessboard ordering of the fractures) is an extremum point of k b u l k .
In absolutely the same manner, we can show that rectangle-cluster ordering of the fractures is also an extremum point of k b u l k . Since k b u l k at chess-board ordering is much higher than in the case of rectangle-cluster ordering at the same values of h , l , M , it is reasonable to assume that chess-board and rectangle-cluster ordering correspond respectively to maximum and minimum influence of fracturing on k b u l k at the specified h , l , M .
One can see from Figure 3 that the bulk permeability can exceed the rock matrix permeability by more than two orders of magnitude even in the case of disconnected fractures. This implies that a significant difference between bulk permeability of the rocks and matrix permeability (which is measured in laboratory tests [30,31]) is not an argument in favor of an existence of a network of hydraulically connected fractures, which extends throughout the rock massif.

4. Characteristics of Fracturing of Nizhnekansky Massif Rocks (Eniseisky Site, Krasnoyarsk Region, Russia)

Granitoid massif Nizhnekansky is located in the Krasnoyarsk region (Russia). It is considered a potential territory for the development of a federal underground repository of high-level and intermediate-level nuclear waste with long-lived radionuclides [3,38]. Studies on the rock matrix were carried out on six samples from different sites and different depths of the granitoid massif. The core samples were 38–52 mm in diameter and about 150 mm in length. Petrographic and mineral–chemical studies have shown that the rocks are liable to metamorphic (amphibolite facies with quartz, feldspars, biotite, amphiboles) and low-temperature hydrothermal–metasomatic alterations (chloritization, sericitization and argillization), which are correspondingly accompanied by ductile (gneiss texture with characteristic foliation) and brittle (cataclastic, brecciated textures and microcracks filled by carbonate, chlorite, sericite and clay minerals) deformations [39,40]. A brief description of sample compositions and data on their permeability are presented in the Table 1, from which one can see that permeability of the samples (i.e., permeability of the rock matrix) does not exceed 3 × 10−18 m2.
Data of bulk permeability of rocks of the Yeniseisky site which is considered at present as the most promising place for development of the vitrified HLW repository are provided in [41]. Measurements were carried out in exploratory boreholes by pumping tests at depths up to 700 m. Results of the measurements are shown in Figure 5 (a and b where permeability k is expressed though hydraulic conductivity f as k = f μ / ( ρ g ) , where ρ is groundwater density, g is acceleration due to gravity; k 1.16 10 13 f in the considered case if permeability unit is m2, and water conductivity unit is m/day, as in Figure 5b).

5. Discussion

Recalculation of the data in Figure 5b shows that permeability of rocks does not exceed 10−15 m2 beneath the depth of 300 m. This is higher by almost three orders of magnitude than the rock matrix permeability. Hence, one can expect that the bulk permeability is caused mostly by fractures. However, comparison of different curves in Figure 5b shows that peaks on one curve are absent at the same depth on curves obtained by tests in neighboring boreholes though the distance between them does not usually exceed 500 m. This evidences that fractures do not form hydraulically connected clusters (network) that extend throughout the whole massif [41]. Hence, a part of the groundwater flow path is within the rock matrix. Therefore, mechanical retention of radiocolloid is quite probable in this part of the Nizhnekansky granitoid massif, where research is being conducted to create the first federal underground repository of high-level nuclear waste in Russia.

6. Conclusions

The main mechanism of radioactive pollution propagation from an underground repository is caused by the transport of radionuclides by groundwaters to the biosphere. The groundwater flows in the earth’s crust through connected systems of pore and fracture voids. These systems are called flow channels. Radionuclides can be carried by the groundwater as a dissolved component or in the form of colloid particles with attached radionuclides. Colloidal form can be more mobile in geological media than radionuclide ions. However, the rocks can mechanically retain radioactive colloid particles if dimensions of cross-sections of the filtration channels are less than dimensions of colloid particles. Hence, the possibility of mechanical retention of radioactive colloid remains even in the case of fracturing increasing bulk permeability of the rocks by a few orders of magnitude. This statement agrees with data from laboratory examination of rocks from the Nizhnekansky granitoid massif, which has been selected as a site for the construction of the first federal underground repository of vitreous high-level radioactive waste in Russia.

Author Contributions

Conceptualization, V.I.M., V.A.P. and S.V.Y.; methodology, M.I.O.; formal analysis, V.I.M.; software, V.I.M.; experimental studies, V.A.P. and S.V.Y.; resources, V.V.P.; data curation, V.A.P., S.V.Y. and V.V.P.; validation, S.V.Y.; writing—original draft preparation, V.I.M., V.A.P., S.V.Y. and M.I.O.; writing—review and editing, M.I.O. and S.V.Y.; supervision, V.A.P.; funding acquisition, V.A.P.; project administration, V.A.P.; All authors have read and agreed to the published version of the manuscript.

Funding

This research was funded by the Government of the Russian Federation, state assignment “Geoecological problems of nuclear power engineering” (01 January 2021–30 December 2023).

Institutional Review Board Statement

Not applicable.

Informed Consent Statement

Not applicable.

Data Availability Statement

Data supporting reported results can be found in referenced publications.

Conflicts of Interest

The authors declare no conflict of interest.

References

  1. Krauskopf, K.B. Geology of high-level nuclear waste disposal. Ann. Rev. Earth Planet. Sci. 1988, 16, 173–200. [Google Scholar] [CrossRef]
  2. National Research Council. End Points for Spent Nuclear Fuel and High-Level Radioactive Waste in Russia and the United States; Committee on End Points for Spent Nuclear Fuel and High-Level Radioactive Waste in Russia and the United States; National Academies Press: Washington, DC, USA, 2003; p. 137. [CrossRef]
  3. Laverov, N.P.; Yudintsev, S.V.; Kochkin, B.T.; Malkovsky, V.I. The Russian Strategy of using Crystalline Rock as a Repository for Nuclear Waste. Elements 2016, 12, 253–256. [Google Scholar] [CrossRef]
  4. Savage, D. The Scientific and Regulatory Basis for the Geological Disposal of Radioactive Waste; John Wiley&Sons: Chichester, UK, 1995; p. 437. [Google Scholar]
  5. Niemeyer, M.J.; Hugi, M.; Smith, P.; Zuidema, P. Kristallin-I performance assessment: First results from sensitivity studies. In Geological Disposal of Spent Fuel, High Level and Alpha Bearing Wastes; International Atomic Energy Agency: Vienna, Austria, 1993; pp. 297–308. [Google Scholar]
  6. Bear, J. Modeling flow and contaminant transport in fractured rocks. In Flow and Contaminant Transport in Fractured Rocks; Bear, J., Tsang, C.-F., De Marsily, G., Eds.; Academic Press, Inc.: San Diego, CA, USA, 1993; pp. 1–38. [Google Scholar]
  7. Neretnieks, I. Solute transport in fractured rock–applications to radionuclide waste repositories. In Flow and Contaminant Transport in Fractured Rocks; Bear, J., Tsang, C.-F., De Marsily, G., Eds.; Academic Press, Inc.: San Diego, CA, USA, 1993; pp. 39–128. [Google Scholar]
  8. Ewing, R.C.; Whittleston, R.A.; Yardley, B.W.D. Geological disposal of nuclear waste: A primer. Elements 2016, 12, 233–237. [Google Scholar] [CrossRef] [Green Version]
  9. Petrov, V.A.; Lespinasse, M.; Poluektov, V.V.; Ustinov, S.A.; Minaev, V.A. Scale effect in a fluid-conducting fault network. Geol. Ore Depos. 2019, 61, 293–305. [Google Scholar] [CrossRef]
  10. Barenblatt, G.; Zheltov, I.; Kochina, I. Basic concepts in the theory of seepage of homogeneous liquids in fissured rocks [strata]. J. Appl. Math. Mech. 1960, 24, 1286–1303. [Google Scholar] [CrossRef]
  11. Tsang, C.-F. Tracer transport in fracture systems. In Flow and Contaminant Transport in Fractured Rocks; Bear, J., Tsang, C.-F., De Marsily, G., Eds.; Academic Press, Inc.: San Diego, CA, USA, 1993; pp. 237–266. [Google Scholar]
  12. Berre, I.; Doster, F.; Keilegavlen, E. Flow in fractured porous media: A review of conceptual models and discretization approaches. Transp. Porous Media 2019, 130, 215–236. [Google Scholar] [CrossRef] [Green Version]
  13. Wong, D.L.; Doster, F.; Geiger, S.; Francot, E.; Gouth, F. Fluid flow characterization framework for naturally fractured reservoirs using small-scale fully explicit models. Transp. Porous Media 2020, 134, 399–434. [Google Scholar] [CrossRef]
  14. De Marsily, G. Quantitative Hydrogeology; Academic Press: Orlando, FL, USA, 1986; p. 440. [Google Scholar]
  15. McKinley, I.G.; Alexander, W.R. Assessment of radionuclide retardation: Uses and abuses of natural analogue studies. J. Contam. Hydrol. 1993, 13, 249–259. [Google Scholar] [CrossRef]
  16. Malkovsky, V.I.; Pek, A.A. Effect of elevated velocity of particles in groundwater flow and its role in colloid-facilitated transport of radionuclides in underground medium. Transp. Porous Media 2009, 78, 277–294. [Google Scholar] [CrossRef]
  17. Penrose, W.R.; Polzer, W.L.; Essington, E.H.; Nelson, D.M.; Orlandini, K.A. Mobility of plutonium and americium through a shallow aquifer in a semiarid region. Environ. Sci. Technol. 1990, 24, 228–234. [Google Scholar] [CrossRef]
  18. McCarthy, J.F.; Czerwinski, K.R.; Sanford, W.E.; Jardine, P.M.; Marsh, J.D. Mobilization of transuranic radionuclides from disposal trenches by natural organic matter. J. Contam. Hydrol. 1998, 30, 49–77. [Google Scholar] [CrossRef]
  19. McCarthy, J.F.; Sanford, W.E.; Stafford, P.L. Lanthanide field tracers demonstrate enhanced transport of transuranic radionuclides by natural organic matter. Environ. Sci. Technol. 1998, 32, 3901–3906. [Google Scholar] [CrossRef]
  20. Kersting, A.B.; Efurd, D.W.; Finnegan, D.L.; Rokop, D.J.; Smith, D.K.; Thompson, J.L. Migration of plutonium in ground water at the Nevada Test Site. Nature 1999, 397, 56–59. [Google Scholar] [CrossRef] [PubMed]
  21. Nyhan, J.W.; Drennon, B.J.; Abeele, W.V.; Wheeler, M.L.; Purtymun, W.D.; Trujillo, G.; Herrera, W.J.; Booth, J.W. Distribution of plutonium and americium beneath a 33-yr-old liquid waste disposal site. J. Environ. Qual. 1985, 14, 501–509. [Google Scholar] [CrossRef]
  22. Zachara, J.M.; Smith, S.C.; Liu Ch McKinley, J.P.; Serne, R.J.; Gassman, P.L. Sorption of Cs+ to micaceous subsurface sediments from the Hanford site, U.S.A. Geochim. Cosmochim. Acta 2002, 66, 193–211. [Google Scholar] [CrossRef] [Green Version]
  23. Smith, D.K.; Finnegan, D.L.; Bowen, S.M. An inventory of long-lived radionuclides residual from underground nuclear testing at the Nevada test site, 1951–1992. J. Environ. Radioact. 2003, 67, 35–51. [Google Scholar] [CrossRef]
  24. Malkovsky, V.I.; Yudintsev, S.V.; Aleksandrova, E.V. Leaching of radioactive waste surrogates from a glassy matrix and migration of the leaching products in gneisses. Radiochemistry 2018, 60, 648–656. [Google Scholar] [CrossRef]
  25. Honeyman, B.D. Colloidal culprits in contamination. Nature 1999, 397, 23–24. [Google Scholar] [CrossRef] [PubMed]
  26. Inagaki, Y.; Sakata, H.; Furuya, H.; Idemitsu, K.; Arima, T.; Banba, T.; Maeda, T.; Matsumoto, S.; Tamura, Y.; Kikkawa, S. Effects of water redox conditions and presence of magnetite on leaching of Pu and Np from HLW glass. Mater. Res. Soc. Proc. 1998, 506, 177–184. [Google Scholar] [CrossRef]
  27. Buck, E.C.; Bates, J.K. Microanalysis of colloids and suspended particles from nuclear waste glass alteration. Appl. Geochem. 1999, 14, 635–659. [Google Scholar] [CrossRef]
  28. Ojovan, M.; Lee, W.E. Glassy wasteforms for nuclear waste immobilization. Metall. Mater. Trans. A 2011, 42, 837–851. [Google Scholar] [CrossRef] [Green Version]
  29. Ojovan, M.I.; Petrov, V.A.; Yudintsev, S.V. Glass crystalline materials as advanced nuclear wasteforms. Sustainability 2021, 13, 4117. [Google Scholar] [CrossRef]
  30. Yudintsev, S.V.; Pervukhina, A.M.; Mokhov, A.V.; Malkovsky, V.I.; Stefanovsky, S.V. Influence of phosphate glass recrystallization on the stability of a waste matrix to leaching. Dokl. Earth Sci. 2017, 473, 427–432. [Google Scholar] [CrossRef]
  31. Mal’kovskii, V.I.; Yudintsev, S.V.; Pervukhina, A.M. Leaching of degraded preservative matrices, based on sodium aluminophosphate glasses, for high-level wastes. At. Energy 2018, 123, 177–182. [Google Scholar] [CrossRef]
  32. Malkovsky, V.I.; Yudintsev, S.V.; Aleksandrova, E.V. Influence of Na-Al-Fe-P glass alteration in hot non-saturated vapor on leaching of vitrified radioactive wastes in water. J. Nucl. Mater. 2018, 508, 212–218. [Google Scholar] [CrossRef]
  33. Degueldre, C.; Benedicto, A. Colloid generation during water flow transients. Appl. Geochem. 2012, 27, 1220–1225. [Google Scholar] [CrossRef]
  34. Missana, T.; Alonso, U.; Fernández, A.M.; García-Gutiérrez, M. Analysis of the stability behaviour of colloids obtained from different smectite clays. Appl. Geochem. 2018, 92, 180–187. [Google Scholar] [CrossRef]
  35. Malkovsky, V.I.; Yudintsev, S.V.; Ojovan, M.I.; Petrov, V.A. The influence of radiation on confinement properties of nuclear waste glasses. Sci. Technol. Nucl. Install. 2020, 2020, 8875723. [Google Scholar] [CrossRef]
  36. Bredehoeft, J.D.; Norton, D.L. Mass and energy transport in a deforming Earth’s crust. In The Role of Fluids in Crustal Processes; Geophysics Study Committee, Comission on Geosciences, Environment and Resources, National Research Council; National Academy Press: Washington, DC, USA, 1990; pp. 27–41. [Google Scholar]
  37. Shmonov, V.M.; Mal’kovskii, V.I.; Zharikov, A.V. A Technique for measuring permeability of samples of anisotropic rocks for water and gas. Instrum. Exp. Tech. 2011, 54, 722–728. [Google Scholar] [CrossRef]
  38. Lobanov, N.F.; Beigul, V.P.; Lopatin, P.V.; Ozersky, A.Y. Selection and validation of area for underground research laboratory in Nizhnekansky Massif. Min. J. 2015, 10, 59–63. (In Russian) [Google Scholar] [CrossRef]
  39. Petrov, V.A.; Poluektov, V.V.; Hammer, J.; Zulauf, G. Analysis of mineralogical and deformation-induced transformations of Nizhnekansky Massif rocks to estimate their retention capacity in geological disposal and isolation of radioactive waste. Gorn. Zhurnal—Min. J. 2015, 10, 67–74. (In Russian) [Google Scholar] [CrossRef]
  40. Petrov, V.A.; Siitati-Kauppi, M.; Tikkanen, O.; Sardini, P.; Poluektov, V.V. Preliminary results of C14-PMMA impregnation of Krasnoyarsk rock samples for evaluating the porosity related properties. In Proceedings of the 21th International Conference “Physico-Chemical and Petrophysical Researches in Earth Sciences”, IGEM RAS, Moscow, Russia, 21–23 September 2020; pp. 310–315. [Google Scholar]
  41. Malkovsky, V.I.; Ozerskiy, A.Y. Stochastic model of filtration properties distribution for enclosing rocks of an underground repository of radioactive waste on the basis of pumping tests. In Proceedings of the 15th International Conference “Physico-Chemical and Petrophysical Researches in Earth Sciences”, IGEM RAS, Moscow, Russia, 29 September–1 October 2014; pp. 159–162. [Google Scholar]
Figure 1. Diagram of porous–fractured rocks: (a) chessboard ordering of fractures in a porous permeable rock matrix; (b) recurrent cell of the porous–fractured medium at chessboard ordering of the fractures in the rock matrix.
Figure 1. Diagram of porous–fractured rocks: (a) chessboard ordering of fractures in a porous permeable rock matrix; (b) recurrent cell of the porous–fractured medium at chessboard ordering of the fractures in the rock matrix.
Sustainability 15 00882 g001
Figure 2. Comparison of bulk permeability values calculated numerically with approximating Formula (10). Dashed lines correspond to errors of ±25%.
Figure 2. Comparison of bulk permeability values calculated numerically with approximating Formula (10). Dashed lines correspond to errors of ±25%.
Sustainability 15 00882 g002
Figure 3. Rectangle-cluster ordering of fractures in porous rock matrix.
Figure 3. Rectangle-cluster ordering of fractures in porous rock matrix.
Sustainability 15 00882 g003
Figure 4. Modifications of chessboard ordering of the fractures. (a) chessboard ordering of fractures; (b) chessboard ordering shifted by Δ along the row direction; (c) chessboard ordering shifted by Δ in the opposite direction.
Figure 4. Modifications of chessboard ordering of the fractures. (a) chessboard ordering of fractures; (b) chessboard ordering shifted by Δ along the row direction; (c) chessboard ordering shifted by Δ in the opposite direction.
Sustainability 15 00882 g004
Figure 5. Data of pumping test at the site of the granitoid massif Nizhnekansky, which is selected for the development of the first federal underground repository of high-level radioactive waste in Russia. (a) Positions of the boreholes; (b) hydraulic conductivity of rocks.
Figure 5. Data of pumping test at the site of the granitoid massif Nizhnekansky, which is selected for the development of the first federal underground repository of high-level radioactive waste in Russia. (a) Positions of the boreholes; (b) hydraulic conductivity of rocks.
Sustainability 15 00882 g005
Table 1. Composition and permeability of rock samples 1.
Table 1. Composition and permeability of rock samples 1.
NosSample IndexCompositionPermeability, m2
1K 560.8Granodiorite1.488 × 10−18
2K 613.1Porphyric adamellite2.307 × 10−18
3I 142.6Gneissic granite with metasomatic alterations3.712 × 10−20
4I 491.7Gneissic granite8.201 × 10−19
5I 357.2Quartz diorite3.092 × 10−19
6I 504.6Quartz diorite9.595 × 10−19
1 Note: the sample number corresponds to depth of selection at the Kamenny (K) or Itatsky (I) sites.
Disclaimer/Publisher’s Note: The statements, opinions and data contained in all publications are solely those of the individual author(s) and contributor(s) and not of MDPI and/or the editor(s). MDPI and/or the editor(s) disclaim responsibility for any injury to people or property resulting from any ideas, methods, instructions or products referred to in the content.

Share and Cite

MDPI and ACS Style

Malkovsky, V.I.; Petrov, V.A.; Yudintsev, S.V.; Ojovan, M.I.; Poluektov, V.V. Influence of Rock Structure on Migration of Radioactive Colloids from an Underground Repository of High-Level Radioactive Waste. Sustainability 2023, 15, 882. https://doi.org/10.3390/su15010882

AMA Style

Malkovsky VI, Petrov VA, Yudintsev SV, Ojovan MI, Poluektov VV. Influence of Rock Structure on Migration of Radioactive Colloids from an Underground Repository of High-Level Radioactive Waste. Sustainability. 2023; 15(1):882. https://doi.org/10.3390/su15010882

Chicago/Turabian Style

Malkovsky, Victor I., Vladislav A. Petrov, Sergey V. Yudintsev, Michael I. Ojovan, and Valeri V. Poluektov. 2023. "Influence of Rock Structure on Migration of Radioactive Colloids from an Underground Repository of High-Level Radioactive Waste" Sustainability 15, no. 1: 882. https://doi.org/10.3390/su15010882

Note that from the first issue of 2016, this journal uses article numbers instead of page numbers. See further details here.

Article Metrics

Back to TopTop