Abstract
This report is a background report of the TURVA-2012 safety case report “Assessment of Radionuclide Release Scenarios for the Repository System” (Posiva 2012a). This report gives a comprehensive account of the modelling of radionuclide release from a defective canister and the subsequent migration to the surface groundwater system. The focus of this report is in the radionuclide migration both in the repository near-field and in the repository far-field. Radionuclide releases from the canister and migration through the repository near-field and far-field have also been analysed in the probabilistic sensitivity analysis based on the Monte Carlo simulation method. Those simulations are discussed in a separate report by Cormenzana (2013).
Calculation cases are derived from three different types of scenarios:
i) The base scenario that assumes a single initially defective canister located in a cautiously selected canister position, i.e. selecting the failed canister location such that radionuclide release and transport properties are conservative compared to the statistics over all canister locations. Migration processes and parameter values follow the most likely lines of evolution. Repository safety functions are assumed to perform according to the design basis. Calculation cases defined in the Assessment of Radionuclide Release Scenarios report (Posiva 2012a) are also supplemented by additional calculation cases that are aimed to study variability between different DFN realisations (additional BS-ALL cases), longitudinal dispersion (BS-RC-ld cases) and alternative realisations of the transport classes along the release paths (BS-RC-tc cases).
ii) Variant scenarios that study declined performance of the repository safety functions. These include enhanced corrosion failure and degradation of the buffer under variant geochemical conditions
iii) Disturbance scenarios that analyse influences of unlikely events on the radionuclide release and migration.
Analysis of the variant and disturbance scenarios above are supplemented by a number of complementary cases that aim to develop a better understanding of the modelled system or subsystems. Far-field modelling has not needed to be carried out for all complementary calcultion cases.
The selection of cautious locations for the analysed defective canister in the base scenario is supported by modelling calculation cases where all potential canister locations for the defective canister are considered.
A thorough analysis of the results from the calculation cases is carried out in the Assessment of Radionuclide Release Scenarios report (Posiva 2012a). The present report includes a couple of extensions of the main calculation cases that are not directly discussed in the Assessment of Radionuclide Release Scenarios report. These include analysis that illustrates influence of the stochastic variability on the selection of the cautious canister location and influence of the longitudinal dispersion on the release rates. The selected cautious canister location gives very pessimistic geosphere retention properties relative to the distributions of the transport properties from the analysed alternative DFN models and realisations. The influence on the release rates of the dominating nuclides caused by the longitudinal dispersion and realisation of the transport classes along the geosphere release path appears to be negligible.
Calculation cases are derived from three different types of scenarios:
i) The base scenario that assumes a single initially defective canister located in a cautiously selected canister position, i.e. selecting the failed canister location such that radionuclide release and transport properties are conservative compared to the statistics over all canister locations. Migration processes and parameter values follow the most likely lines of evolution. Repository safety functions are assumed to perform according to the design basis. Calculation cases defined in the Assessment of Radionuclide Release Scenarios report (Posiva 2012a) are also supplemented by additional calculation cases that are aimed to study variability between different DFN realisations (additional BS-ALL cases), longitudinal dispersion (BS-RC-ld cases) and alternative realisations of the transport classes along the release paths (BS-RC-tc cases).
ii) Variant scenarios that study declined performance of the repository safety functions. These include enhanced corrosion failure and degradation of the buffer under variant geochemical conditions
iii) Disturbance scenarios that analyse influences of unlikely events on the radionuclide release and migration.
Analysis of the variant and disturbance scenarios above are supplemented by a number of complementary cases that aim to develop a better understanding of the modelled system or subsystems. Far-field modelling has not needed to be carried out for all complementary calcultion cases.
The selection of cautious locations for the analysed defective canister in the base scenario is supported by modelling calculation cases where all potential canister locations for the defective canister are considered.
A thorough analysis of the results from the calculation cases is carried out in the Assessment of Radionuclide Release Scenarios report (Posiva 2012a). The present report includes a couple of extensions of the main calculation cases that are not directly discussed in the Assessment of Radionuclide Release Scenarios report. These include analysis that illustrates influence of the stochastic variability on the selection of the cautious canister location and influence of the longitudinal dispersion on the release rates. The selected cautious canister location gives very pessimistic geosphere retention properties relative to the distributions of the transport properties from the analysed alternative DFN models and realisations. The influence on the release rates of the dominating nuclides caused by the longitudinal dispersion and realisation of the transport classes along the geosphere release path appears to be negligible.
| Original language | English |
|---|---|
| Publisher | Posiva |
| Number of pages | 336 |
| ISBN (Print) | 978-951-652-240-4 |
| Publication status | Published - 2014 |
| MoE publication type | D4 Published development or research report or study |
Publication series
| Series | Posiva Report |
|---|---|
| Volume | 2014-02 |
| ISSN | 1239-3096 |
Keywords
- safety assessment
- migration
- modelling
- release rate
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