Abstract
Radioactive waste disposal systems for spent nuclear fuel are designed to isolate the radioactive waste from the human environment for long period of time. The isolation is provided by a combination of engineered and natural barriers. Safety assessments are performed to describe and quantify the performance of the individual barriers and the disposal system over long-term periods. These assessments will always be associated with uncertainties. Uncertainties can originate from the variability of natural systems and will also be introduced in the predictive modelling performed to quantitatively evaluate the behaviour of the disposal system as a consequence of the incomplete knowledge about the governing processes. Uncertainties in safety assessments can partly be reduced by additional measurements and research. The aim of this study has been to identify uncertainties in assessments of radiological consequences from the disposal of spent nuclear fuel based on the Swedish KBS-3 concept. The identified uncertainties have been classified with respect to their origin, i.e. in conceptual, modelling and data uncertainties. The possibilities to reduce the uncertainties are also commented upon. In assessments it is important to decrease uncertainties which are of major importance for the performance of the disposal system. These could to some extent be identified
More>>
Wiborgh, M;
Elert, M;
Hoeglund, L O;
Jones, C;
Grundfelt, B;
Skagius, K;
Bengtsson, A
[1]
- Kemakta Konsult AB, Stockholm (Sweden)
Citation Formats
Wiborgh, M, Elert, M, Hoeglund, L O, Jones, C, Grundfelt, B, Skagius, K, and Bengtsson, A.
A review of the uncertainties in the assessment of radiological consequences of spent nuclear fuel disposal.
Sweden: N. p.,
1992.
Web.
Wiborgh, M, Elert, M, Hoeglund, L O, Jones, C, Grundfelt, B, Skagius, K, & Bengtsson, A.
A review of the uncertainties in the assessment of radiological consequences of spent nuclear fuel disposal.
Sweden.
Wiborgh, M, Elert, M, Hoeglund, L O, Jones, C, Grundfelt, B, Skagius, K, and Bengtsson, A.
1992.
"A review of the uncertainties in the assessment of radiological consequences of spent nuclear fuel disposal."
Sweden.
@misc{etde_10118826,
title = {A review of the uncertainties in the assessment of radiological consequences of spent nuclear fuel disposal}
author = {Wiborgh, M, Elert, M, Hoeglund, L O, Jones, C, Grundfelt, B, Skagius, K, and Bengtsson, A}
abstractNote = {Radioactive waste disposal systems for spent nuclear fuel are designed to isolate the radioactive waste from the human environment for long period of time. The isolation is provided by a combination of engineered and natural barriers. Safety assessments are performed to describe and quantify the performance of the individual barriers and the disposal system over long-term periods. These assessments will always be associated with uncertainties. Uncertainties can originate from the variability of natural systems and will also be introduced in the predictive modelling performed to quantitatively evaluate the behaviour of the disposal system as a consequence of the incomplete knowledge about the governing processes. Uncertainties in safety assessments can partly be reduced by additional measurements and research. The aim of this study has been to identify uncertainties in assessments of radiological consequences from the disposal of spent nuclear fuel based on the Swedish KBS-3 concept. The identified uncertainties have been classified with respect to their origin, i.e. in conceptual, modelling and data uncertainties. The possibilities to reduce the uncertainties are also commented upon. In assessments it is important to decrease uncertainties which are of major importance for the performance of the disposal system. These could to some extent be identified by uncertainty analysis. However, conceptual uncertainties and some type of model uncertainties are difficult to evaluate. To be able to decrease uncertainties in conceptual models, it is essential that the processes describing and influencing the radionuclide transport in the engineered and natural barriers are sufficiently understood. In this study a qualitative approach has been used. The importance of different barriers and processes are indicated by their influence on the release of some representative radionuclides. (122 refs.) (au).}
place = {Sweden}
year = {1992}
month = {Jun}
}
title = {A review of the uncertainties in the assessment of radiological consequences of spent nuclear fuel disposal}
author = {Wiborgh, M, Elert, M, Hoeglund, L O, Jones, C, Grundfelt, B, Skagius, K, and Bengtsson, A}
abstractNote = {Radioactive waste disposal systems for spent nuclear fuel are designed to isolate the radioactive waste from the human environment for long period of time. The isolation is provided by a combination of engineered and natural barriers. Safety assessments are performed to describe and quantify the performance of the individual barriers and the disposal system over long-term periods. These assessments will always be associated with uncertainties. Uncertainties can originate from the variability of natural systems and will also be introduced in the predictive modelling performed to quantitatively evaluate the behaviour of the disposal system as a consequence of the incomplete knowledge about the governing processes. Uncertainties in safety assessments can partly be reduced by additional measurements and research. The aim of this study has been to identify uncertainties in assessments of radiological consequences from the disposal of spent nuclear fuel based on the Swedish KBS-3 concept. The identified uncertainties have been classified with respect to their origin, i.e. in conceptual, modelling and data uncertainties. The possibilities to reduce the uncertainties are also commented upon. In assessments it is important to decrease uncertainties which are of major importance for the performance of the disposal system. These could to some extent be identified by uncertainty analysis. However, conceptual uncertainties and some type of model uncertainties are difficult to evaluate. To be able to decrease uncertainties in conceptual models, it is essential that the processes describing and influencing the radionuclide transport in the engineered and natural barriers are sufficiently understood. In this study a qualitative approach has been used. The importance of different barriers and processes are indicated by their influence on the release of some representative radionuclides. (122 refs.) (au).}
place = {Sweden}
year = {1992}
month = {Jun}
}