Din avgränsning ger 174 träffar.
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2012:55 Technical Note, Review of SKB’s Radionuclide Transport Methodology
As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to consider whether SKB’s methodology to abstract FEPs (features, events, processes), as well as site information and other data, into assessment models for radionuclide transport is appropriate and sufficient for its...
Innehållstyp: Publikationer -
2012:62 Technical Note, Review of the MARFA Code
As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to review SKB’s MARFA code and consider whether the technical arguments and assumptions used for developing the code are sound, appropriate and adequate to support its use in SR-Site. This Technical Note summarises the...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
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...
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 -
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...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2017:28 SSM’s external experts’ review of SKB’s safety assessment SR-PSU - hydrogeology, geochemistry and bentonite
Main review phase...
Innehållstyp: Publikationer