Filtered generated 161 hits.
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2015:05 Technical Note, Review of uncertainty propagation and sensitivity analysis in SR-Site Main Review Phase
The review assignment SSM2014-2060 “Review of uncertainty and sensi- tivity analysis in SR-Site” addressed three issues: 1. Adequacy of the methods adopted by SKB for conducting sensitivity analyses 2. Approach for use of conservative and best-estimate parameter values 3. Propagation of uncertainty for the corrosion scenario Adequacy of the methods for sensitivity analyses: The sensitivity...
Content type: Publications -
2015:29 Technical Note, Quality Assurance in SKB’s Copper Corrosion Experiments
I Sverige planeras slutförvaring av använt kärnbränsle. Metoden som har utvecklats kallas för KBS-3 och den bygger på tre skyddsbarriärer; kopparkapslar, bentonitlera och det svenska urberget. Det specifika syftet med den här rapporten är att få en förståelse för, och en bedömning av, SKB:s kvalitetssäkring av deras försök...
Content type: Publications -
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.
Content type: Publications -
2015:01 Technical Note, Rock Mechanics - Thermal properties and thermal modelling of the rock in a repository of spent nuclear fuel at Forsmark – Main Review Phase
In preparation for the review of SKB's license application for a disposal of spent nuclear fuel, SSM has conducted a series of modelling studies related to the design, construction and long-term safety of a repository at Forsmark. Several of the presented modelling works are related to the thermal evolution of the repository with time. This report extracts the results from independent SSM...
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 -
2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C
Background Stress corrosion cracking (SCC) can occur in materials from the combined influence of tensile stress and a corrosive environment. It has previously been shown in the literature, that copper can be sensitive to SCC in the presence of sulfide containing water. Since both tensile stresses are present as well as a material were SCC can occur, SCC could potentially be a problem for the...
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 -
2012:37 Technical Note, Selective review of the hydrogeological aspects of SR-Site
This review of the hydrogeology is selective. It focuses on the measurement, interpretation and modelling of the potential repository host rock, that is the rock domain FFM01<-400m. It accepts as reasonably accurate the measurement and representation of the more transmissive parts of the hydrogeological system, particularly the near-surface 150m in the form presented by SKB. SKB have decided...
Content type: Publications