Abstract
Teollisuuden Voima Oy (TVO) is currendy construcing in Finland an underground repository (the VLJ repository) for storage of low- and intermediate-level radioactive wastes generated at the Olkiluoto (TVO I and TVO II) nuclear power plant. Intermediate level wastes will be emplaced inside a large concrete silo, which is the principal engineered barrier in the repository. The primary objective of the investigation is to develop an estimate of the length of time it will take for the silo to degrade due to interaction with groundwater to the point that it fails to perform as designed. A secondary objective is to develop a methodology to estimate the length of time required for radio nuclides to migrate from the region inside the silo through the silo wall and floor to the accessible environment as a function of cement and concrete properties. Chemical modeling techniques using the codes EQ3NR/EQ6 were employed to model the degradation of the repository concrete due to interaction with groundwater, and porous flow and diffusion modeling approaches were taken to: (1) estimate the time it would take groundwater and ions to travel into and out of the silo concrete, and (2) determine how these travel times change as the concrete
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Citation Formats
Alcorn, S R, Christian-Frear, T L, and Wallace, M.
Degradation modelling for the concrete silo in TVO`s VLJ repository.
Finland: N. p.,
1991.
Web.
Alcorn, S R, Christian-Frear, T L, & Wallace, M.
Degradation modelling for the concrete silo in TVO`s VLJ repository.
Finland.
Alcorn, S R, Christian-Frear, T L, and Wallace, M.
1991.
"Degradation modelling for the concrete silo in TVO`s VLJ repository."
Finland.
@misc{etde_10142584,
title = {Degradation modelling for the concrete silo in TVO`s VLJ repository}
author = {Alcorn, S R, Christian-Frear, T L, and Wallace, M}
abstractNote = {Teollisuuden Voima Oy (TVO) is currendy construcing in Finland an underground repository (the VLJ repository) for storage of low- and intermediate-level radioactive wastes generated at the Olkiluoto (TVO I and TVO II) nuclear power plant. Intermediate level wastes will be emplaced inside a large concrete silo, which is the principal engineered barrier in the repository. The primary objective of the investigation is to develop an estimate of the length of time it will take for the silo to degrade due to interaction with groundwater to the point that it fails to perform as designed. A secondary objective is to develop a methodology to estimate the length of time required for radio nuclides to migrate from the region inside the silo through the silo wall and floor to the accessible environment as a function of cement and concrete properties. Chemical modeling techniques using the codes EQ3NR/EQ6 were employed to model the degradation of the repository concrete due to interaction with groundwater, and porous flow and diffusion modeling approaches were taken to: (1) estimate the time it would take groundwater and ions to travel into and out of the silo concrete, and (2) determine how these travel times change as the concrete degrades. The results of the investigation suggest that the hydraulic conductivity of the concrete will decrease over time because of the considerable net volume increase (net porosity decrease) from the chemical interactions. Therefore, it appears likely, based on the geochemical and mass transport models, that the silo win perform as required for at least its 500-year design life, and possibly much longer.}
place = {Finland}
year = {1991}
month = {May}
}
title = {Degradation modelling for the concrete silo in TVO`s VLJ repository}
author = {Alcorn, S R, Christian-Frear, T L, and Wallace, M}
abstractNote = {Teollisuuden Voima Oy (TVO) is currendy construcing in Finland an underground repository (the VLJ repository) for storage of low- and intermediate-level radioactive wastes generated at the Olkiluoto (TVO I and TVO II) nuclear power plant. Intermediate level wastes will be emplaced inside a large concrete silo, which is the principal engineered barrier in the repository. The primary objective of the investigation is to develop an estimate of the length of time it will take for the silo to degrade due to interaction with groundwater to the point that it fails to perform as designed. A secondary objective is to develop a methodology to estimate the length of time required for radio nuclides to migrate from the region inside the silo through the silo wall and floor to the accessible environment as a function of cement and concrete properties. Chemical modeling techniques using the codes EQ3NR/EQ6 were employed to model the degradation of the repository concrete due to interaction with groundwater, and porous flow and diffusion modeling approaches were taken to: (1) estimate the time it would take groundwater and ions to travel into and out of the silo concrete, and (2) determine how these travel times change as the concrete degrades. The results of the investigation suggest that the hydraulic conductivity of the concrete will decrease over time because of the considerable net volume increase (net porosity decrease) from the chemical interactions. Therefore, it appears likely, based on the geochemical and mass transport models, that the silo win perform as required for at least its 500-year design life, and possibly much longer.}
place = {Finland}
year = {1991}
month = {May}
}