Filtered generated 160 hits.
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2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Content type: Publications -
2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022
The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...
Content type: Publications -
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 -
2012:06 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 -
2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues
The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...
Content type: Publications -
2012:21 Technical Note, Initial Review Phase for SKBs Safety Assessment SR-Site: Corrosion of Copper
The uniform and localized corrosion treatments as well as stress corrosion cracking positions currently considered by SKB have been examined with the objective of identifying key unresolved issues or gaps, needs and opportunities. In conjunction with the review of the SKB reports listed in Appendix 1, there has been some consideration of the broader literature. This summary highlights the...
Content type: Publications