Filtered generated 161 hits.
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2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspective Background The concept that the Swedish nuclear power industry plans to utilise for the final disposal spent nuclear fuel is called KBS-3 method, which is based on three different barriers to prevent spreading of radioactive substances: copper canisters, bentonite buffers and the surrounding Swedish bedrock. In the current KBS-3 design, the spent nuclear fuel will be placed in...
Content type: Publications -
2024:13 Technical Note, Review of recent research activities conducted by SKB relating to hydro geological aspects of the disposal of radioactive waste
SSM perspective Background The Swedish Radiation Safety Authority (SSM) examines the Swedish Nuclear Fuel Company’s (SKB) applications in a step-wise review and approval process according to the government’s licence conditions under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a geological disposal facilities. As part of the review, SSM commissions...
Content type: Publications -
The international radiation protection school in Stockholm attracts participants from over 20 countries
For five days, at Stockholm University, international early and mid-career radiation protection experts gather to develop their knowledge in radiation protection. The course alternates between theory and practice and provides in-depth knowledge and understanding on the structure and application of the international system for radiation protection.
Content type: News -
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 -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Content type: Publications -
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 -
2014:54 Technical Note, Further Modelling Comparison of Simple Reference Biosphere Models with the LDF Modelling Approach – Main Review Phase
This Technical Note describes further use of simple reference biosphere models for SSM’s review of the Landscape Dose Factor (LDF) approach adopted by SKB in the SR‑Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site. Simple biosphere models for the Forsmark site under temperate climate conditions were previously developed for SSM’s review and are...
Content type: Publications -
2014:58 Technical Note, Rock Mechanics - Assessing probability and extent of blind faults and fault-end growth around the KBS-3 repository at Forsmark – Main Review Phase
To get a general understanding of the stability conditions of the fault and deformation zone inventory at Forsmark a reactivation potential analysis was carried out. At present-day stress conditions the deformation zones are stable and show no large deformations or detected seismicity. Any changes in stress, and in particular increase of differential stress on deformation zones, might cause...
Content type: Publications -
2014:47 Technical Note, Assessment of groundwater salinity evolution at repository depth and especially the impact of dilute water infiltration
Groundwater compositions entering deposition holes in the repository will be progressively diluted over time because of expected changes of topographic and climatic conditions at Forsmark. This is a long-term safety issue because very dilute water could destabilise compacted bentonite and erode buffer, leading to advective movement of sulphide-containing water to the canister surface. SKB’s...
Content type: Publications -
2014:55 Technical Note, Further Reproduction of SKB’s Calculation Cases and Independent
Som en del av säkerhetsanalysen SR-Site presenterar SKB modellresultat som illustrerar kapseln och buffertens säkerhetsfunktioner. I var och en av de fem beräkningsfallen är delar av kapsel och/eller buffert frånvarande i modellen av slutförvarssystemet. Modellresultaten jämförs inte med säkerhetskriterier eftersom beräkningsfallen innehåller...
Content type: Publications