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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...

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Autores principales: Kim, Won-Seok, Han, Sangsoo, Ahn, Jinmo, Um, Wooyong
Formato: Online Artículo Texto
Lenguaje:English
Publicado: Springer Netherlands 2018
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.
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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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