Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste Repository
Deep and stable geological formations with low permeability have been considered for high level waste definitive repository. A common problem is the modeling of radionuclide migration in a fractured medium. Initially, we considered a system consisting of a rock matrix with a single planar fracture i...
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| Format: | Article |
| Language: | English |
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Wiley
2013-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2013/827961 |
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| author | Claudia Siqueira da Silveira Antonio Carlos Marques Alvim Jose de Jesus Rivero Oliva |
| author_facet | Claudia Siqueira da Silveira Antonio Carlos Marques Alvim Jose de Jesus Rivero Oliva |
| author_sort | Claudia Siqueira da Silveira |
| collection | DOAJ |
| description | Deep and stable geological formations with low permeability have been considered for high level waste definitive repository. A common problem is the modeling of radionuclide migration in a fractured medium. Initially, we considered a system consisting of a rock matrix with a single planar fracture in water saturated porous rock. Transport in the fracture is assumed to obey an advection-diffusion equation, while molecular diffusion is considered the dominant mechanism of transport in porous matrix. The partial differential equations describing the movement of radionuclides were discretized by finite difference methods, namely, fully explicit, fully implicit, and Crank-Nicolson schemes. The convective term was discretized by the following numerical schemes: backward differences, centered differences, and forward differences. The model was validated using an analytical solution found in the literature. Finally, we carried out a simulation with relevant spent fuel nuclide data with a system consisting of a horizontal fracture and a vertical fracture for assessing the performance of a hypothetical repository inserted into the host rock. We have analysed the bentonite expanded performance at the beginning of fracture, the quantified radionuclide released from a borehole, and an estimated effective dose to an adult, obtained from ingestion of well water during one year. |
| format | Article |
| id | doaj-art-36c47266f7974d5d9c606752ce0334c6 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2013-01-01 |
| publisher | Wiley |
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| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-36c47266f7974d5d9c606752ce0334c62025-02-03T01:09:14ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832013-01-01201310.1155/2013/827961827961Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste RepositoryClaudia Siqueira da Silveira0Antonio Carlos Marques Alvim1Jose de Jesus Rivero Oliva2Graduate Program of Nuclear Engineering (COPPE), Federal University of Rio de Janeiro, 21941-841 Rio de Janeiro, RJ, BrazilGraduate Program of Nuclear Engineering (COPPE), Federal University of Rio de Janeiro, 21941-841 Rio de Janeiro, RJ, BrazilDepartment of Nuclear Engineering, Polytechnic School, Federal University of Rio de Janeiro, 21941-841 Rio de Janeiro, RJ, BrazilDeep and stable geological formations with low permeability have been considered for high level waste definitive repository. A common problem is the modeling of radionuclide migration in a fractured medium. Initially, we considered a system consisting of a rock matrix with a single planar fracture in water saturated porous rock. Transport in the fracture is assumed to obey an advection-diffusion equation, while molecular diffusion is considered the dominant mechanism of transport in porous matrix. The partial differential equations describing the movement of radionuclides were discretized by finite difference methods, namely, fully explicit, fully implicit, and Crank-Nicolson schemes. The convective term was discretized by the following numerical schemes: backward differences, centered differences, and forward differences. The model was validated using an analytical solution found in the literature. Finally, we carried out a simulation with relevant spent fuel nuclide data with a system consisting of a horizontal fracture and a vertical fracture for assessing the performance of a hypothetical repository inserted into the host rock. We have analysed the bentonite expanded performance at the beginning of fracture, the quantified radionuclide released from a borehole, and an estimated effective dose to an adult, obtained from ingestion of well water during one year.http://dx.doi.org/10.1155/2013/827961 |
| spellingShingle | Claudia Siqueira da Silveira Antonio Carlos Marques Alvim Jose de Jesus Rivero Oliva Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste Repository Science and Technology of Nuclear Installations |
| title | Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste Repository |
| title_full | Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste Repository |
| title_fullStr | Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste Repository |
| title_full_unstemmed | Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste Repository |
| title_short | Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste Repository |
| title_sort | radionuclide transport in fractured rock numerical assessment for high level waste repository |
| url | http://dx.doi.org/10.1155/2013/827961 |
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