Waste glass behavior in a loamy soil of a wet repository site

Ojovan, Michael I.; Ojovan, N. V.; Startceva, I. V.; Tchuikova, G.N; Golubeva, Zoya I.; Barinov, A. S.

doi:10.1016/s0022-3115(01)00593-1

Cited by 21 publications

(25 citation statements)

References 2 publications

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“…We found very good similarity with leach coefficient, D e , from our previous work [10,11]. The results well fitted to semi empirical model proposed by author [7,9]. A linear regression fitting the experimental results leads to minor influence of variable t, which parameter A 2 is not significant in the linear regression analysis.…”

Section: Resultssupporting

confidence: 84%

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Mathematical Modelling of Immobilization of Radionuclides 137Cs and 60Co in Concrete Matrix

Plećaš¹,

Dimović²

2009

TOWMJ

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Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using an empirical method employing a polynomial equation. To assess the safety for disposal of radioactive waste-cement composition, the leaching of 137 Cs and 60 Co, from a waste composite into a surrounding fluid has been studied. Leaching tests were carried out in accordance with a method recommended by IAEA. Determination of retardation factors, K F and coefficients of distribution, k d , using a simplified mathematical model for analyzing the migration of radionuclides, has been developed. Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using an empirical method employing a polynomial equation. In our experiment we have analyzed mechanism of 137 Cs and 60 Co leaching values during a period of 60 days. Results presented in this paper are examples of values obtained in a 25 year mortar and concrete testing project, which will influence the design of the engineered trenches system for a future central Serbian radioactive waste storage centre.

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Section: Resultssupporting

confidence: 84%

“…To overcome this problem, should adopt a semiempirical method to obtain a model that describes the longterm leaching characteristics of a waste component by polynomial equation [6,7]. In this model, the cumulative amount of contaminant leached is expressed by:…”

Section: Radionuclide Migration Through Porous Materials and Modellinmentioning

confidence: 99%

Mathematical Modelling of Immobilization of Radionuclides 137Cs and 60Co in Concrete Matrix

Plećaš¹,

Dimović²

2009

TOWMJ

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“…Dedicated experiments are carried out to identify leaching behaviour of cementitious wasteforms and to demonstrate their acceptance for storage and disposal [10,[14][15][16][17][18][19][20]. Both laboratory tests [14][15][16][17] and long-term tests using conditions similar to those expected in a disposal environment are currently used [10,[18][19][20][21]. For the assessment of long term performance and safety of a near-surface disposal system, knowledge of the long term behaviour of actual radioactive wasteforms is needed.…”

Section: Introductionmentioning

confidence: 99%

Long-term field and laboratory leaching tests of cemented radioactive wastes

Ojovan

Varlackova²,

Golubeva³

et al. 2011

Journal of Hazardous Materials

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Experiments with real and simulated radioactive cementitious wasteforms were set up to compare the leaching behaviour of cementitious wasteforms containing nuclear power plant operational waste in field and laboratory test conditions. Experiments revealed that the average annual 137 Cs leach rate in deionised water was about thirty-five times greater compared with the measured average value for the 1 st year of the field test. Cumulative leached fraction of 137 Cs for 1 st year (3.74%) was close to values reported in literature for similar laboratory experiments in deionized water, however more than two orders of magnitude higher than the 1 st year leached fraction of 137 Cs in the repository test (0.01%). Therefore, to compare field and laboratory test results, a scaling factor is required in order to account for surface to volume factor difference, multiplied by a temperature factor and a leach rate decrease coefficient related to the ground water composition.

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“…The gaps between the blocks were filled with river sand in order to prevent direct contact with the surrounding loam and to facilitate infiltration of ground water, which accumulated in the trap. The testing conditions are characterized by water-saturated soil with pH 7.6-7.7 and mineral content 600 mg/liter (see Table 1) [7]. The ground water was pumped out for radiometric, radiochemical, and chemical analysis.…”

mentioning

confidence: 99%

“…Sampling was done periodically, usually twice a month. The volume of the water sample v j and the specific activity a ij were taken into account in the calculation of the total amount of leached radionuclides [7]. The total volume of the ground water in contact with the glass was calculated as the sum of the samples extracted j over time t:…”

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confidence: 99%

Results of 16 Years of Testing of Vitrified Intermediate-Level Wastes from the Kursk Nuclear Power Plant

Дмитриев¹,

Barinov²,

Ozhovan³

et al. 2005

At Energy

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Data from a field experiment performed over a period of 16 years at the testing site of the Moscow Scientific and Industrial Association Radon, studying intermediate-level activity K-26 glass with surface storage, are analyzed. The average 137 Cs leach rate was 2.2·10 -7 g/(cm 2 ·day) over 16 years of testing. The effective mutual diffusion coefficient of cesium was found to be 5·10 -21 m 2 /sec and the rate of hydrolysis of the glass framework was found to be 0.1 µm/yr. The calculation showed that the maximum possible amount of leached radionuclides from glass does not exceed 20 kBq over 300 yr.In the last few years, there has been great interest in vitrifying intermediate-and low-level wastes [1][2][3]. In the USA, a program is being conducted on vitrifying low-level wastes with the proposed volume of glass obtained greater than 160,000 m 3 [1], and in South Korea a plant for vitrifying the operational wastes from a nuclear power plant is being put into operation [2]. Our country also is a leader in using glass for immobilizing radioactive wastes, including low-and intermediate-level [3]. The scales of application of glass are substantial, and correspondingly interest in assessing glass as an immobilizing matrix for radionuclides is increasing. The present work analyzes data from 16 years of field tests of K-26 borosilicate glass [4]. This glass contains a substantial amount of sodium, which makes this glass of special interest for analyzing the safety of surface storage [1,5].Field Tests. K-26 borosilicate glass was developed for immobilizing intermediate-level wastes containing no boron, i.e., wastes from nuclear power plants with RBMK reactors [6]. The composition of the glass is as follows (mass %): other oxides 6.2. The density of the glass is 2.46 g/cm 3 . Several tons of this glass were fabricated for immobilizing wastes from the Kursk nuclear power plant [3,6]. The concentration of the main radionuclide 137 Cs in the wastes in the glass obtained was 3.73·10 6 Bq/kg [6]. Field tests were started in 1987, when six glass blocks with a total mass of 190 kg were buried in an experimental repository at a depth of 1.7 m below the seasonal frost line 0.7 m [7]. Glass blocks, 30 cm high, were placed inside a 40 cm deep stainless steel pallet equipped with a trap for ground water. The gaps between the blocks were filled with river sand in order to prevent direct contact with the surrounding loam and to facilitate infiltration of ground water, which accumulated in the trap. The testing conditions are characterized by water-saturated soil with pH 7.6-7.7 and mineral content 600 mg/liter (see Table 1) [7]. The ground water was pumped out for radiometric, radiochemical, and chemical analysis. Sampling was done periodically, usually twice a month. The volume of the water sample v j and the specific activity a ij were taken into account in the calculation of the total amount of leached radionuclides [7]. The total volume of the ground water in contact with the glass was calculated as the sum of the samples extracted j ...

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Waste glass behavior in a loamy soil of a wet repository site

Cited by 21 publications

References 2 publications

Mathematical Modelling of Immobilization of Radionuclides 137Cs and 60Co in Concrete Matrix

Mathematical Modelling of Immobilization of Radionuclides 137Cs and 60Co in Concrete Matrix

Long-term field and laboratory leaching tests of cemented radioactive wastes

Results of 16 Years of Testing of Vitrified Intermediate-Level Wastes from the Kursk Nuclear Power Plant

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