Din avgränsning ger 565 träffar.
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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...
Innehållstyp: Publikationer -
2014:40 Technical Note, Review of Performance Confirmation Programs and Potential Roles in SSM’s Current Review of SKB’s License Application – Main Review Phase
The initial license application of a repository concept for disposal of radioactive waste is based on extensive site characterization, baseline monitoring, development of disposal designs and engineered barriers, test data on engineered barriers, and the integration of a series of models representing processes controlling the containment, release and migration of radionuclides from the...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2014:59 Technical Note, Relation between earthquake magnitude, fracture length and fracture shear displacement in the KBS-3 repository at Forsmark – Main Review Phase
This study addresses one of several scenarios that could impair the physical integrity of the repository of spent nuclear fuel at the Forsmark site. Two sources of threat are: i) events due to thermal loading on the rock mass by the heat from canisters with spent nuclear fuel, and ii) seismic events, i.e. earthquakes, at the nearby deformation zones and zones intersecting the repository area.
Innehållstyp: Publikationer -
2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...
Innehållstyp: Publikationer -
2011:26 The influence of temperature and fluid pressure on the fracture network evolution around deposition holes of a KBS-3V concept at Forsmark, Sweden
In preparation for the review of SKB’s license application for disposal of spent nuclear fuel, SSM is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at about 500 m depth and embedded in clay. Thus, the rock, the clay and the copper canister...
Innehållstyp: Publikationer -
2008:11 Discrete-Feature Modelling of Groundwater Flow and Solute Transport for SR-Can Review
Review External review contribution in support of SKI's and SSI's review of SR-Can. The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for...
Innehållstyp: Publikationer -
2008:47 Selected Models for Key Processes in a Nuclear Waste Repository
The conceptual design of the disposal of spent nuclear fuel in Sweden is based on a multibarrier system. In the KBS-3 concept, the bentonite buffer is a barrier with the primary purpose of surrounding and protecting the canister. The bentonite buffer is expected to prevent or minimise the water exchange with the surrounding rock and protect the canister against mechanical damages caused by...
Innehållstyp: Publikationer -
2009:08 Shear-induced Fracture Slip and Permeability Change - Implications for Long-term Performance of a Deep Geological Repository
Opening of fractures induced by shear dilation or normal deformation can be a significant source of fracture permeability change in jointed rock, which is important for the performance assessment of geological repositories for spent nuclear fuel. As the repository generates heat and later cools the fluid-carrying ability of the rocks becomes a dynamic variable during the lifespan of the...
Innehållstyp: Publikationer -
2007:30 Modelling the Interaction of Low pH Cements and Bentonite
Concrete and cement are used in constructions as well as in conditioning of waste inrepositories for radioactive waste. It is well known that in the hyperalkaline conditions (pH > 12) of standard cement pore fluids, there is potential for deleterious effects upon the host rock and other EBS materials, notably bentonite, in geological repositories. Low pH cements are beginning to be considered...
Innehållstyp: Publikationer