Filtered generated 146 hits.
-
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 -
2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility
Background For final storage of spent nuclear fuel it is suggested by the Swedish nuclear fuel and waste management company (SKB) to emplace the nuclear fuel into copper canisters which are surrounded by bentonite clay at approximately 500 meters’ depth into granitic rock. After emplacement of the canisters Bentonite swelling due to water saturation and hydrostatic pressure build up the...
Content type: Publications -
2013:27 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures
The design codes for anchorage of equipment in concrete structures have been developed since the time the Swedish power plants were designed. Furthermore, the design basis has been updated and in some cases new mechanical loads have been added. As a consequence, it can be difficult for some anchorages to meet the requirements of today. In the design of anchorage equipment the beneficial effect...
Content type: Publications -
2012:03 The IAEA Integrated Regulatory Review Service Mission to Sweden in February 2012
The Swedish Government decided on January 22, 2009 to mandate the Swedish Radiation Safety Authority, SSM, to apply for an international review of the Author-ity and its areas of supervision, an ‘IRRS’ (Integrated Regulatory Review Service) carried out by the International Atomic Energy Agency (IAEA). On February 25, 2009, SSM made a formal request to the IAEA for an IRRS in Sweden. The time...
Content type: Publications -
2012:18 Technical Note, SR-Site Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Contribution to the Initial Review Phase
This review has focussed mainly on the modelling of the Engineered Barrier System (EBS) evolution, which includes coupled thermal, hydraulic, mechanical and chemical (THMC) processes. Additionally, the role of the EBS in the wider safety case was reviewed, including its treatment in scenarios and its representation in conceptual models since this provided the motivation for the modelling work...
Content type: Publications -
2012:33 Technical Note, Review of Groundwater Chemistry in SKB’s Safety Assessment SR-Site
This initial review examined SKB’s characterization of groundwater chemistry at the Forsmark site and its evolution during long time periods under different possible climates in the future. The review considered whether the geochemical data provided by SKB are reasonable and sufficient and whether the methods used by SKB for projecting geochemical conditions into the future are appropriate.
Content type: Publications -
2012:36 Technical Note, Documentation and Traceability of Data in SKB’s Safety Assessment SR-Site: Initial Review Phase
On 16th March 2011SKB applied for a licence to construct and operate a spent nuclear fuel encapsulation facility in Oskarshamn Municipality and a final repository for the encapsulated fuel at Forsmark in Östhammar Municipality. SKB’s SR-Site safety assessment for the spent fuel repository is currently being reviewed by the Swedish Radiation Safety Authority, SSM, and its external experts...
Content type: Publications -
2012:34 Technical Note, Review of FEP Handling in the SR-Site Safety Assessment: Initial Review Phase
On 16th March 2011 the Swedish Nuclear Fuel and Waste Management Company, SKB, submitted applications for licences to construct a spent nuclear fuel encapsulation facility in Oskarshamn and a repository for final disposal of the encapsulated fuel in Forsmark. SKB’s applications are currently being reviewed by the Swedish Radiation Safety Authority, SSM, and the Land and Environmental Court in...
Content type: Publications