1
|
Zhang X, Ma F, Dai Z, Wang J, Chen L, Ling H, Soltanian MR. Radionuclide transport in multi-scale fractured rocks: A review. JOURNAL OF HAZARDOUS MATERIALS 2022; 424:127550. [PMID: 34740158 DOI: 10.1016/j.jhazmat.2021.127550] [Citation(s) in RCA: 22] [Impact Index Per Article: 11.0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Subscribe] [Scholar Register] [Received: 08/09/2021] [Revised: 10/07/2021] [Accepted: 10/16/2021] [Indexed: 06/13/2023]
Abstract
Significant progress has been achieved on radionuclide transport in fractured rocks due to worldwide urgent needs for geological disposal of high-level radioactive waste (HLW). Transport models designed with accurately constrained parameters are a fundamental prerequisite to assess the long-term safety of repositories constructed in deep formations. Focusing on geological disposal systems of HLW, this study comprehensively reviews the behavoir of radionuclides and transport processes in multi-scale fractured rocks. Three issues in transport modeling are emphasized: 1) determining parameters of radionuclide transport models in various scales from laboratory- to field-scale experiments, 2) upscaling physical and chemical parameters across scales, and 3) characterizing fracture structures for radionuclide transport simulations. A broad spectrum of contents is covered relevant to radionuclide transport, including laboratory and field scale experiments, analytical and numerical solutions, parameter upscaling, and conceptual model developments. This paper also discusses the latest progress of radionuclide migration in multi-scale fractured rocks and the most promising development trends in the future. It provides valuable insights into understanding radionuclide transport and long-term safety assessment for HLW geological repository.
Collapse
Affiliation(s)
- Xiaoying Zhang
- College of Construction Engineering, Jilin University, Changchun 130026, China
| | - Funing Ma
- College of Construction Engineering, Jilin University, Changchun 130026, China
| | - Zhenxue Dai
- College of Construction Engineering, Jilin University, Changchun 130026, China; Engineering Research Center of Geothermal Resources Development Technology and Equipment, Ministry of Education, Jilin University, Changchun, China.
| | - Ju Wang
- CNNC Key Laboratory on Geological Disposal of High-Level Radioactive Waste, Beijing Research Institute of Uranium Geology, Beijing 100029, China; CAEA Innovation Center on Geological Disposal of High Level Radioactive Waste, China
| | - Liang Chen
- CNNC Key Laboratory on Geological Disposal of High-Level Radioactive Waste, Beijing Research Institute of Uranium Geology, Beijing 100029, China; CAEA Innovation Center on Geological Disposal of High Level Radioactive Waste, China
| | - Hui Ling
- CNNC Key Laboratory on Geological Disposal of High-Level Radioactive Waste, Beijing Research Institute of Uranium Geology, Beijing 100029, China; CAEA Innovation Center on Geological Disposal of High Level Radioactive Waste, China
| | - Mohamad Reza Soltanian
- Department of Geology, University of Cincinnati, Cincinnati, OH, USA; Departments of Environmental Engineering, University of Cincinnati, Cincinnati, OH, USA
| |
Collapse
|
2
|
Guzman J, Maximov S, Escarela-Perez R, López-García I, Moranchel M. Analytical solution to the diffusion, sorption and decay chain equation in a saturated porous medium between two reservoirs. JOURNAL OF ENVIRONMENTAL RADIOACTIVITY 2015; 139:163-170. [PMID: 25464053 DOI: 10.1016/j.jenvrad.2014.10.003] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 07/18/2014] [Revised: 09/30/2014] [Accepted: 10/07/2014] [Indexed: 06/04/2023]
Abstract
The diffusion and distribution coefficients are important parameters in the design of barrier systems used in radioactive repositories. These coefficients can be determined using a two-reservoir configuration, where a saturated porous medium is allocated between two reservoirs filled by stagnant water. One of the reservoirs contains a high concentration of radioisotopes. The goal of this work is to obtain an analytical solution for the concentration of all radioisotopes in the decay chain of a two-reservoir configuration. The analytical solution must be obtained by taking into account the diffusion and sorption processes. Concepts such as overvalued concentration, diffusion and decay factors are employed to this end. It is analytically proven that a factor of the solution is identical for all chains (considering a time scaling factor), if certain parameters do not change. In addition, it is proven that the concentration sensitivity, due to the distribution coefficient variation, depends of the porous medium thickness, which is practically insensitive for small porous medium thicknesses. The analytical solution for the radioisotope concentration is compared with experimental and numerical results available in literature.
Collapse
Affiliation(s)
- Juan Guzman
- Departamento de Energía, Universidad Autónoma Metropolitana-Azcapotzalco, Av. San Pablo 180 Col. Reynosa Tamaulipas, México, D.F. 02200, Mexico.
| | - Serguei Maximov
- Instituto Tecnológico de Morelia, Av. Tecnológico #1500, Lomas de Santiaguito, Morelia, Michoacán 58120, Mexico; On sabbatical leave, Universidad Autónoma Metropolitana, Azcapotzalco, México, D.F. 02200, Mexico
| | - Rafael Escarela-Perez
- Departamento de Energía, Universidad Autónoma Metropolitana-Azcapotzalco, Av. San Pablo 180 Col. Reynosa Tamaulipas, México, D.F. 02200, Mexico
| | - Irvin López-García
- Departamento de Energía, Universidad Autónoma Metropolitana-Azcapotzalco, Av. San Pablo 180 Col. Reynosa Tamaulipas, México, D.F. 02200, Mexico
| | - Mario Moranchel
- Escuela Superior de Física y Matemáticas, Instituto Politécnico Nacional, Av. Instituto Politécnico Nacional s/n, U. P. Adolfo López Mateos, Col. San Pedro Zacatenco, México, D.F. 07738, Mexico
| |
Collapse
|
3
|
Guzmán J, Alvarez-Ramirez J, Escarela-Pérez R, Vargas RA. Diffusion and decay chain of radioisotopes in stagnant water in saturated porous media. JOURNAL OF ENVIRONMENTAL RADIOACTIVITY 2014; 135:100-107. [PMID: 24814719 DOI: 10.1016/j.jenvrad.2014.03.015] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 11/29/2013] [Revised: 03/21/2014] [Accepted: 03/21/2014] [Indexed: 06/03/2023]
Abstract
The analysis of the diffusion of radioisotopes in stagnant water in saturated porous media is important to validate the performance of barrier systems used in radioactive repositories. In this work a methodology is developed to determine the radioisotope concentration in a two-reservoir configuration: a saturated porous medium with stagnant water is surrounded by two reservoirs. The concentrations are obtained for all the radioisotopes of the decay chain using the concept of overvalued concentration. A methodology, based on the variable separation method, is proposed for the solution of the transport equation. The novelty of the proposed methodology involves the factorization of the overvalued concentration in two factors: one that describes the diffusion without decay and another one that describes the decay without diffusion. It is possible with the proposed methodology to determine the required time to obtain equal injective and diffusive concentrations in reservoirs. In fact, this time is inversely proportional to the diffusion coefficient. In addition, the proposed methodology allows finding the required time to get a linear and constant space distribution of the concentration in porous mediums. This time is inversely proportional to the diffusion coefficient. In order to validate the proposed methodology, the distributions in the radioisotope concentrations are compared with other experimental and numerical works.
Collapse
Affiliation(s)
- Juan Guzmán
- Departamento de Energía, Universidad Autónoma Metropolitana-Azcapotzalco, Av. San Pablo 180 Col. Reynosa Tamaulipas, México, D.F. 02200, Mexico.
| | - Jose Alvarez-Ramirez
- División de Ciencias Básicas e Ingeniería, Universidad Autónoma Metropolitana-Iztapalapa, Av. San Rafael Atlixco 186 Col. Vicentina, México, D.F. 09340, Mexico
| | - Rafael Escarela-Pérez
- Departamento de Energía, Universidad Autónoma Metropolitana-Azcapotzalco, Av. San Pablo 180 Col. Reynosa Tamaulipas, México, D.F. 02200, Mexico
| | - Raúl Alejandro Vargas
- Escuela Superior de Física y Matemáticas, Instituto Politécnico Nacional, Av. Instituto Politécnico Nacional s/n, U.P. Adolfo López Mateos, Col. San Pedro Zacatenco, México, D.F. 07738, Mexico
| |
Collapse
|
4
|
Kamran K, van Soestbergen M, Pel L. Electrokinetic Salt Removal from Porous Building Materials Using Ion Exchange Membranes. Transp Porous Media 2012. [DOI: 10.1007/s11242-012-0083-0] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
|
5
|
Chen CL, Wang TH, Lee CH, Teng SP. The development of a through-diffusion model with a parent-daughter decay chain. JOURNAL OF CONTAMINANT HYDROLOGY 2012; 138-139:1-14. [PMID: 22771814 DOI: 10.1016/j.jconhyd.2012.06.002] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 03/13/2012] [Revised: 05/28/2012] [Accepted: 06/04/2012] [Indexed: 06/01/2023]
Abstract
A valid performance assessment of radioactive waste repositories strongly depends on the reliability of nuclide transport parameters, including distribution and diffusion coefficients. To reduce the waste produced and time spent conducting diffusion experiments, a robust model is required to accurately interpret the experiment results. Therefore, we developed a through-diffusion model with parent-daughter nuclide decay chain. We validated our model through comparisons with the Moridis model (Moridis, 1999) and Bharat model (Bharat et al., 2009), assessing our model and these two models using the distribution of parent nuclide concentrations. This strongly supports the rationality and functionality of extending our proposed model to daughter nuclides. In this study, we derived analytical solutions for the parent nuclides of the through-diffusion experiment using the multicompartment (MC) model. We also propose a simplified formula for estimating the apparent diffusion coefficient of parent nuclides based on the analytical solutions. Through numerical experiments, we verified the feasibility of the formula. Our models are useful for determining the apparent diffusion coefficient of daughter nuclides when conducting through-diffusion experiments with parent-daughter nuclide decay chains. Additionally, the proposed models offer the advantages of saving time and reducing experimental waste.
Collapse
Affiliation(s)
- Chin-Lung Chen
- Department of Engineering and System Science, National Tsing Hua University, Taiwan.
| | | | | | | |
Collapse
|
6
|
Lu X, Tervola P, Viljanen M. A new analytical method to solve the heat equation for a multi-dimensional composite slab. ACTA ACUST UNITED AC 2005. [DOI: 10.1088/0305-4470/38/13/004] [Citation(s) in RCA: 35] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/11/2022]
|
7
|
|