Filtered generated 146 hits.
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2017:31 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – rock engineering and concrete barriers
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 the...
Content type: Publications -
2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Ali R. Massih, Lars Olof Jernkvist SSM English...
Content type: Publications -
2015:48 Technical Note, Supplementary review of SKB’s further RFI response
Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen (1984:3) om kärnteknisk verksamhet om uppförande, innehav och drift av ett slutförvar för använt kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta...
Content type: Publications -
2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te
Groundwater sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide concentrations which are assumed to apply throughout the long-term analysis period. The distribution is based on expert judgement in the selection of samples that are regarded as...
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 -
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 -
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...
Content type: Publications -
2014:47 Technical Note, Assessment of groundwater salinity evolution at repository depth and especially the impact of dilute water infiltration
Groundwater compositions entering deposition holes in the repository will be progressively diluted over time because of expected changes of topographic and climatic conditions at Forsmark. This is a long-term safety issue because very dilute water could destabilise compacted bentonite and erode buffer, leading to advective movement of sulphide-containing water to the canister surface. SKB’s...
Content type: Publications -
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...
Content type: Publications