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Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility
Batch adsorption, batch diffusion, and flow-through column experiments were conducted using groundwater and fractured rock collected in unsaturated zone to increase our understanding of sorption and transport behavior of radionuclides. Increasing K(d) values were observed in the sequence (90)Sr, (99...
Autores principales: | , , , |
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Formato: | Online Artículo Texto |
Lenguaje: | English |
Publicado: |
Springer Netherlands
2018
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Materias: | |
Acceso en línea: | https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6510849/ https://www.ncbi.nlm.nih.gov/pubmed/29796958 http://dx.doi.org/10.1007/s10653-018-0123-y |
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author | Kim, Won-Seok Han, Sangsoo Ahn, Jinmo Um, Wooyong |
author_facet | Kim, Won-Seok Han, Sangsoo Ahn, Jinmo Um, Wooyong |
author_sort | Kim, Won-Seok |
collection | PubMed |
description | Batch adsorption, batch diffusion, and flow-through column experiments were conducted using groundwater and fractured rock collected in unsaturated zone to increase our understanding of sorption and transport behavior of radionuclides. Increasing K(d) values were observed in the sequence (90)Sr, (99)Tc, and (3)H regardless of the geological media tested. For all sorbing radionuclides, K(d) values for the fracture-filling/coating material were observed to be higher than those for without fracture-filling/coating material regardless of the groundwater. These higher K(d) values are the result of zeolite mineral in filling/coating material of fractured rock. The batch diffusion and flow-through column experiments were also conducted using the same fractured rock sample, and the results of diffusion and column experiments showed similar trend of radionuclide sorption and transport to sorption experiment. In this study, sorption K(d) of radionuclide was determined and used to increase our understanding of radionuclide retardation through fracture-filling/coating materials. |
format | Online Article Text |
id | pubmed-6510849 |
institution | National Center for Biotechnology Information |
language | English |
publishDate | 2018 |
publisher | Springer Netherlands |
record_format | MEDLINE/PubMed |
spelling | pubmed-65108492019-05-28 Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility Kim, Won-Seok Han, Sangsoo Ahn, Jinmo Um, Wooyong Environ Geochem Health Article Batch adsorption, batch diffusion, and flow-through column experiments were conducted using groundwater and fractured rock collected in unsaturated zone to increase our understanding of sorption and transport behavior of radionuclides. Increasing K(d) values were observed in the sequence (90)Sr, (99)Tc, and (3)H regardless of the geological media tested. For all sorbing radionuclides, K(d) values for the fracture-filling/coating material were observed to be higher than those for without fracture-filling/coating material regardless of the groundwater. These higher K(d) values are the result of zeolite mineral in filling/coating material of fractured rock. The batch diffusion and flow-through column experiments were also conducted using the same fractured rock sample, and the results of diffusion and column experiments showed similar trend of radionuclide sorption and transport to sorption experiment. In this study, sorption K(d) of radionuclide was determined and used to increase our understanding of radionuclide retardation through fracture-filling/coating materials. Springer Netherlands 2018-05-23 2019 /pmc/articles/PMC6510849/ /pubmed/29796958 http://dx.doi.org/10.1007/s10653-018-0123-y Text en © The Author(s) 2018 Open AccessThis article is distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution, and reproduction in any medium, provided you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. |
spellingShingle | Article Kim, Won-Seok Han, Sangsoo Ahn, Jinmo Um, Wooyong Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility |
title | Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility |
title_full | Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility |
title_fullStr | Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility |
title_full_unstemmed | Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility |
title_short | Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility |
title_sort | investigation of (3)h, (99)tc, and (90)sr transport in fractured rock and the effects of fracture-filling/coating material at lilw disposal facility |
topic | Article |
url | https://www.ncbi.nlm.nih.gov/pmc/articles/PMC6510849/ https://www.ncbi.nlm.nih.gov/pubmed/29796958 http://dx.doi.org/10.1007/s10653-018-0123-y |
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