Modeling of radionuclide transport in porous media: A review of recent studies
Source abstract
Abstract
Abstract An overview of recent studies in which the transport of radionuclides in porous materials has been recently modeled is provided. The focus is on the modeling based on balance equations whose results could be used in nuclear waste management for the prediction of long-term behavior and assessment of safety standards. Values of key transport parameters, especially diffusion coefficients, are given and experimental techniques from which these can be determined are outlined. Critical remarks on the modeling and difficulties in the comparison of parameters from various studies are pointed out in the conclusion. Describing a rather wide picture ranging from parameters to experiments and to numerical models, the review might provide a contribution to the understanding and a stimulation for the improvement in the modeling of radionuclide transport.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Groundwater flow and contamination studies · Radioactive element chemistry and processing · Soil and Unsaturated Flow
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (100+)
Show source-provided references
1. A review of the retention mechanisms of redox-sensitive radionuclides in multi-barrier systems10.1016/j.apgeochem.2018.12.001 ↗
2. Concrete and cement composites used for radioactive waste deposition10.1016/j.jenvrad.2017.08.012 ↗
3. The effect of stagnant water zones on retarding radionuclide transport in fractured rocks: an extension to the Channel Network Model10.1016/j.jhydrol.2016.07.031 ↗
4. Recent advances in nuclear power: a review10.1016/j.pnucene.2008.05.001 ↗
5. Development of system for evaluating concrete strength deterioration due to radiation and resultant heat
6. I. Maruyama, O. Kontani, S. Sawada, O. Sato, G. Igarashi, M. Takizawa, Evaluation of irradiation effects on concrete structure – background and preparation of neutron irradiation test. Proceedings of the ASME 2013 Power Conference POWER2013, article 98114. July 29-August 1, 2013, Boston, Massachusetts, USA.
7. A numerical model for concrete strength change under neutron and gamma-ray irradiation10.3151/jact.14.144 ↗
8. Radiation damage evaluation on concrete shielding for nuclear physics experiments10.1007/s12356-011-0023-7 ↗
9. Radiation damage evaluation on concrete within a facility for selective production of exotic species (SPES project)10.1016/j.jhazmat.2011.07.079 ↗
10. Macroscale and mesoscale analysis of concrete as a multiphase material for biological shields against nuclear radiation10.1002/nag.2222 ↗
11. A review on radiation damage in concrete for nuclear facilities: from experiments to modeling
12. Radiation effects on clay mineral properties10.1016/j.clay.2008.07.032 ↗
13. Radiation shielding of concrete containing zeolite10.1016/j.radmeas.2010.04.012 ↗
14. Gamma-ray shielding properties of concrete including barite at different energies10.1016/j.pnucene.2010.04.006 ↗
15. Photon attenuation coefficients of concrete includes barite in different rate10.1016/j.anucene.2010.04.001 ↗
16. Effects of α-radiation on a direct disposal system for spent nuclear fuel – (1) review of research into the effects of α-radiation on the spent nuclear fuel, canisters and outside canisters10.1080/00223131.2015.1018362 ↗
17. Radiation effects in crystalline ceramics for the immobilization of high-level waste and plutonium10.1557/JMR.1998.0205 ↗
18. Depth profiles of radioactive cesium in soil using a scraper plate over a wide area surrounding the Fukushima Dai-ichi Nuclear Power Plant10.1016/j.jenvrad.2014.10.001 ↗
19. Inter-comparison of dynamic models for radionuclide transfer to marine biota in a Fukushima accident scenario10.1016/j.jenvrad.2015.12.006 ↗
20. A preliminary assessment of the potential for use caesium-137 to estimate rates of soil erosion in the Loess Plateau of China10.1080/02626669009492427 ↗
21. A simplified 137Cs transport model for estimating erosion rates in undisturbed soil10.1016/j.jenvrad.2008.03.001 ↗
22. Experimental and numerical investigations of effect of column length on retardation factor determination: a case study of cesium transport in crushed granite10.1016/j.jhazmat.2008.05.076 ↗
23. Uncertainty and sensitivity analysis of radionuclide migration through the engineered barriers of deep geological repository: case of RBMK-1500SNF10.1016/j.ress.2014.11.011 ↗
24. Materials and processes for the effective capture and immobilization of radioiodine: a review10.1016/j.jnucmat.2015.11.038 ↗
25. A single-site reactive transport model of Cs+ for the in situ diffusion and retention (DR) experiment10.1007/s12665-015-4419-2 ↗
26. Radionuclide diffusion into undisturbed and altered crystalline rocks10.1180/minmag.2012.076.8.32 ↗
27. Behavior of HPC nuclear waste disposal structures in leaching environment10.1016/j.nucengdes.2010.11.002 ↗
28. Montmorillonite colloids: II. Colloidal size dependency on radionuclide adsorption10.1016/j.clay.2016.01.017 ↗
29. The transport of U- and Th-series nuclides in a sandy unconfined aquifer10.1016/S0016-7037(00)00617-7 ↗
30. 2-D numerical simulation of radionuclide transport in the lower Yangtze River10.1016/S1001-6058(11)60294-1 ↗
31. Radionuclide transport in shallow groundwater10.1016/j.pnucene.2015.06.023 ↗
32. Hydrologic issues associated with nuclear waste repositories10.1002/2015WR017641 ↗
33. Radionuclide interaction with clays in dilute and heavily compacted systems: a critical review10.1021/es203025q ↗
34. Long-term performance of contacting concrete and smectite clay in deep disposal of highly radioactive waste10.2495/SDP-V11-N5-740-750 ↗
35. ‘Geo’chemical research: a key building block for nuclear waste disposal safety cases10.1016/j.jconhyd.2008.09.012 ↗
36. Long-term geochemical evolution of the near field repository: insights from reactive transport modelling and experimental evidences10.1016/j.jconhyd.2008.09.021 ↗
37. Utilization of Slovak bentonites in deposition of high-level radioactive waste and spent nuclear fuel10.1007/s10967-011-0987-0 ↗
38. Analysis of parameter identifiability of the in situ diffusion and retention (DR) experiment10.1016/j.pce.2010.04.012 ↗
39. Identifiability of diffusion and retention parameters of anionic tracers from the diffusion and retention (DR) experiment10.1016/j.jhydrol.2012.04.032 ↗
40. A global sensitivity analysis of two-phase flow between fractured crystalline rock and bentonite with application to spent nuclear fuel disposal10.1016/j.jconhyd.2015.07.006 ↗
41. Influence of fracture networks on radionuclide transport from solidified waste forms10.1016/j.nucengdes.2013.12.048 ↗
42. Conceptual and numerical models of solute diffusion around a HLW repository in clay10.1016/j.pce.2011.07.014 ↗
43. On the relative importance of input factors in mathematical models: safety assessment for nuclear waste disposal10.1198/016214502388618447 ↗
44. An overview of Task 6 of the Äspö Task Force: modelling groundwater and solute transport: improved understanding of radionuclide transport in fractured rock10.1007/s10040-008-0416-9 ↗
45. Impact of water consumption and saturation-dependent corrosion rate on hydrogen generation and migration from an intermediate-level radioactive waste repository10.1007/s11242-011-9803-0 ↗
46. Naus · 2010
47. Scale dependence of sorption coefficients for contaminant transport in saturated fractured rock10.1029/2008GL036516 ↗
48. Upscaling retardation factor in hierarchical porous media with multimodal reactive mineral facies10.1016/j.chemosphere.2012.10.105 ↗
49. Monte Carlo simulation of radionuclide migration in fractured rock for the performance assessment of radioactive waste repositories10.1016/j.ress.2012.10.002 ↗
50. Nuclide transport of decay chain in the fractured rock medium: a model using continuous time Markov process10.1016/0306-4549(94)00045-G ↗
51. Colloid-facilitated plutonium transport in fractured tuffaceous rock10.1021/acs.est.7b00968 ↗
52. Implementation of a time-domain random-walk method into a discrete element method to simulate nuclide transport in fractured rock masses10.1155/2017/5940380 ↗
53. Nuclear wasteform materials: atomistic simulation case studies10.1016/j.jnucmat.2013.05.012 ↗
54. Solute transport in a single fracture with negligible matrix permeability: 1. fundamental mechanisms10.1007/s10040-003-0268-2 ↗
55. Fickian diffusion of radionuclides for engineered containment barriers: diffusion coefficients, porosities, and complicating issues10.1016/j.enggeo.2012.10.014 ↗
56. Crank · 1975
57. Laboratory diffusion testing for waste disposal—a review10.1016/0169-7722(91)90028-Y ↗
58. Diffusion od radionuclides in concrete and concrete-bentonite systems10.1016/0169-7722(95)00046-1 ↗
59. Diffusion pathways in crystalline rock—examples from Äspö-diorite and fine-grained granite10.1016/S0169-7722(98)00114-4 ↗
60. Effects of biotite distribution on cesium diffusion in granite10.1016/0009-2541(93)90100-W ↗
61. Diffusion and sorption of cesium, strontium and iodine in water-saturated cement10.13182/NT88-A34082 ↗
62. A high-resolution abrasive method for determining diffusion profiles of sorbing radionuclides in dense argillaceous rocks10.1016/j.apradiso.2005.02.001 ↗
63. Solute transport properties of compacted Ca-bentonite used in FEBEX project10.1016/S0169-7722(00)00143-1 ↗
64. Simultaneous estimation of effective and apparent diffusion coefficients in compacted bentonite10.1016/S0169-7722(02)00113-4 ↗
65. Analysis of dual diffusion and non-linear adsorption isotherm with a time lag method10.1023/A:1008959517075 ↗
66. The diffusion of ions through water-saturated cement10.1007/BF01026986 ↗
67. Determination of diffusion coefficients based on Fick's Second Law for various boundary conditions10.1524/ract.1988.4445.2.245 ↗
68. Diffusion of uranium in compacted sodium bentonite10.1016/0013-7952(90)90020-2 ↗
69. Diffusion of HTO, 36Cl– and 125I– in Opalinus clay samples from Mont Terri: effect of confining pressure10.1016/S0169-7722(02)00114-6 ↗
70. Effect of confining pressure on the diffusion of HTO, 36Cl– and 125I– in a layered argillaceous rock (Opalinus Clay): diffusion perpendicular to the fabric10.1016/S0883-2927(03)00047-7 ↗
71. Long-term diffusion experiment at Mont Terri: first results from field and laboratory data10.1016/j.clay.2003.09.007 ↗
72. Diffusion and retention of sodium and strontium in Opalinus clay: comparison of sorption data from diffusion and batch sorption measurements, and geochemical calculations10.1016/j.apgeochem.2005.08.008 ↗
73. Anisotropic diffusion in layered argillaceous rocks: a case study with Opalinus clay10.1021/es049937g ↗
74. Tritium and iodide diffusion through Opalinus clay10.1557/PROC-663-1179 ↗
75. In-situ diffusion of HTO, 22Na+, Cs+ and I– in Opalinus Clay at the Mont Terri underground rock laboratory10.1524/ract.92.9.757.54988 ↗
76. Diffusion of tritiated water and 22Na+ through non-degraded hardened cement pastes10.1016/S0169-7722(02)00112-2 ↗
77. A physicochemical characterisation and geochemical modelling approach for determining pore water chemistries in argillaceous rocks10.1016/S0016-7037(97)00387-6 ↗
78. Bear · 2013
79. Migration characteristics of radionuclides 85+89Sr2+, 134Cs+, 125I–, 75SeO32– and 152+154Eu(III) in Chinese soils. Column investigation10.1023/A:1026222512462 ↗
80. A simplified approach to evaluation of column experiments as a tool for determination of radionuclide transport parameters in rock-groundwater or soil-groundwater systems10.1007/s10967-014-3898-z ↗
81. Simplified modeling in dynamic column technique for the determination of radionuclide transport parameters in systems of solid granular materials and groundwater10.1007/s10967-016-4958-3 ↗
82. Vertical migration of radio-caesium derived from the Fukushima Dai-ichi Nuclear Power Plant accident in undisturbed soils of grassland and forest10.1016/j.gexplo.2016.07.023 ↗
83. Contaminant transport in fractured porous media: analytical solution for a single fracture10.1029/WR017i003p00555 ↗
84. Solute transport in a single fracture with negligible matrix permeability: 1. mathematical formalism10.1007/s10040-003-0269-1 ↗
85. 1-D modelling of radionuclide migration through permeable and fractured rock for arbitrary length decay chains using numerical inversion of Laplace transform10.1016/0306-4549(88)90011-4 ↗
86. Diffusion in the rock matrix: an important factor in radionuclide retardation?10.1029/JB085iB08p04379 ↗
87. Contaminant transport in fractured porous media: analytical solution for a system of parallel fractures10.1029/WR018i006p01634 ↗
88. Sudicky · Reply. Water Resour. Res. · 1984 · 20 · 132310.1029/WR020i009p01323 ↗
89. Contaminant transport in fractured porous media: analytical solution for a two-member decay chain in a single fracture10.1029/WR020i007p01021 ↗
90. Solute transport through fractured media 1. The effect of matrix diffusion10.1029/WR016i004p00719 ↗
91. Chalk groundwater tritium anomaly – a possible explanation10.1016/0022-1694(75)90045-1 ↗
92. Comment on “Contaminant transport in fractured porous media: analytical solutions for a system of parallel fractures” by E.A. Sudicky and E.O. Frind, Water10.1029/WR020i009p01321 ↗
93. Transport of a two-member decay chain in a single fracture: simplified analytical solution for two radionuclides with the same transport properties10.1029/1999WR900341 ↗
94. Radionuclide transport in fast channels in crystalline rock10.1029/WR022i008p01247 ↗
95. Migration of radionuclides from a high-level radioactive waste repository in deep geological formations10.1007/s12665-014-3525-x ↗
96. Linear response concept combining advection and limited rock matrix diffusion in a fracture network transport model10.1029/96WR02508 ↗
97. Significance of fracture rim zone heterogeneity for tracer transport in crystalline rock10.1029/2009WR007755 ↗
98. Contaminant transport in a single fracture: periodic boundary and flow conditions10.1029/WR025i005p00774 ↗
99. Flow and nuclide transport in fractured media: the importance of the flow-wetted surface for radionuclide migration10.1016/0169-7722(93)90050-3 ↗
100. An analytical model for radionuclide transport in a single fracture: considering nonequilibrium matrix sorption10.13182/NT93-A34768 ↗