Filtered generated 146 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 -
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 -
2025:02 INCLUDE: Including (local) stakeholder participation in the regulatory mission – a future challenge
SSM perspective Background The primary focus of SSM’s communication with stakeholders in relation to the disposal of spent nuclear fuel and nuclear waste has for several years been on formal consultation processes surrounding the Swedish nuclear power industry’s research and development programme as well as SKB’s licence applications under the Nuclear Activities Act. Following licensing by...
Content type: Publications -
2016:16 Technical Note, Possible influence from stray currents from high voltage DC power transmission on copper canisters
Main Review Phase Introduction As part of the Swedish Radiation Safety Authority’s (SSM) review of the Swedish Nuclear Fuel and Waste management company (SKB) license application for a final storage for spent nuclear fuel, SSM has asked for complementary information regarding the effect of stray currents from high voltage cables on copper corrosion (SSM 2012). SKB therefore has performed an...
Content type: Publications -
2016:21 The effect of a glaciation on East Central Sweden: case studies on present glaciers and analyses of landform data
The Swedish Radiation Safety Authority reviews and assesses applications for geological repositories for nuclear waste. When assessing the long term safety of the repositories it is important to consider possible future developments of climate and climate-related processes. Especially the next glaciation is important for the review and assessment for the long term safety of the spent nuclear...
Content type: Publications -
2016:12 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – engineered barriers, engineering geology and chemical inventory
Background The Swedish Radiation Safety Authority (SSM) received an application for the expansion of SKB's final repository for low and intermediate level waste at Forsmark (SFR) on the 19 December 2014. SSM is tasked with the review of the application and will issue a statement to the government who will decide on the matter. An important part of the application is SKB's assessment of...
Content type: Publications -
2016:30 Measurement of Parameter Values for Predicting Corrosion Phenomena on Copper in Swedish HLNW Repositories
Passivity breakdown and pitting on pure copper, the assumed material for the canisters for the isolation of high-level nuclear waste in Sweden, has been studied in simulated, sulphide- and chloride containing granitic rock groundwater and the data are interpreted in terms of the Point Defect Model (PDM). The results indicated that a sulphide barrier layer forms on the copper surface, and that...
Content type: Publications -
2016:08 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – hydrogeological and chemical aspects
Initial review phase SSM English Initial review phase...
Content type: Publications -
2015:49 Technical Note, Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Canister Corrosion Calculations in SR-Site
Projektets syfte Projektet syftar till att granska olika beräkningsfall för korrosion av kopparkapseln som rapporterats i SKB TR-10-66 och som sammanfattas i SKB TR-11-01. Arbetet omfattar en analys av beräkningsfall relaterade till korrosionshastigheten för intakt buffert, delvis eroderad buffert och för advektiva förhållanden i bufferten. Målsättningen...
Content type: Publications -
2015:47 GEMA-Site 1: Model description and example application
Background In 2011 the Swedish Nuclear Fuel and Waste Management Company (SKB) submitted an assessment of the long-term safety of a KBS-3 geological disposal facility for spent nuclear fuel in Forsmark, Sweden. This assessment, the SR-Site project, supports the licence application of SKB to build such a final disposal facility. The biosphere dose assessment carried out as part of SR-Site...
Content type: Publications