Filtered generated 755 hits.
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2012:32 Technical Note, Groundwater Chemistry in SKB’s Safety Assessment SR-Site: Initial Review
This preliminary review of SR-Site is focused specifically on the treatment of groundwater chemistry in the description of the Forsmark site and in the long-term safety of a deep geological repository at Forsmark. Data for the chemical and isotopic compositions of groundwaters have contributed to a site descriptive model (SDM) for Forsmark. In that SDM, groundwater chemistry is interpreted...
Content type: Publications -
2012:17 Technical Note, Corrosion of copper canister
It is expected that the inflow of ground water to the deposition holes and tunnels in the Forsmark repository will be very slow. Thus, it might take some few hundred years up to thousand years before the deposition holes are filled with ground water and it might take 6000 years or more before the bentonite buffer is fully water saturated and pressurized. The copper canisters will therefore...
Content type: Publications -
2012:59 Technical Note, Initial review phase – Dose Assessment Methodology
This report has been prepared as part of the Initial Review Phase of SKB’s SR-Site performance assessment of the long-term safety of the KBS-3 geological disposal facility (GDF) proposed for construction at Forsmark. The review addresses the methodology employed in the dose assessment calculations of SR-Site. In this respect the review has a natural focus upon biosphere modelling aspects of...
Content type: Publications -
2011:10e Review and evaluation of the Swedish Nuclear Fuel and Waste Management Company’s RD&D Programme 2010. Statement to the Government and summary of the review report
In accordance with Section 25 of the Ordinance (1984:14) on Nuclear Activities (Nuclear Activities Ordinance), the Swedish Radiation Safety Authority (SSM) shall review and assess the research, development and demonstration programme (RD&D programme) that the reactor licensees are obligated to establish in accordance with the Act (1984:3) on Nuclear Activities (Nuclear Activities Act).
Content type: Publications -
2012:46 Technical Note, Review of Landscape Models used in SR-Site
As part of SSM’s Initial Review phase of SKB’s SR-Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site, Quintessa was given the assignment to consider whether the landscape models and supporting data utilised by SKB are appropriate and fit for purpose. This Technical Note summarises the findings of Quintessa’s review. SKB’s approach to the...
Content type: Publications -
2012:61 Geochemical Constraints on Buffer Pore Water Evolution and Implications for Erosion
Mineralogical data from the Forsmark Site show that smectite and calcite occur at all depths in Forsmark fractures, with no evidence for removal/dissolution by previous glacial episodes. This natural analogue information implies that these minerals may not have been eroded/dissolved during previous glacial episodes. Available thermodynamic data suggest that repository-depth Forsmark...
Content type: Publications -
2012:06 Decommissioning Cost Assessment
The future costs for dismantling, decommissioning and handling of associated radioactive waste of nuclear installations represents substantial liabilities. It is the generations that benefits from the use of nuclear installations that shall carry the financial burden. Nuclear waste programmes have occasionally encountered set-backs related to the trust from society. This has resulted in...
Content type: Publications -
2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures
The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...
Content type: Publications -
2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C
The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...
Content type: Publications -
2011:09 Is Copper Immune to Corrosion When in Contact With Water and Aqueous Solutions?
The KBS-3concept implies that spent nuclear fuel is placed in copper canisters surrounded by clay and finally placed approximately 500 m down from surface into granitic bedrock, in order to isolate the spent nuclear fuel from humans and environment for very long time scales (i.e. millions of years). The concept is based on the multi-barrier principle, in this respect the barriers are the...
Content type: Publications