Filtered generated 65 hits.
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2017:33 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – dose assessment, Kd-values, and safety analysis methodology
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 -
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 -
2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2
Background In the design of anchorage equipment in concrete structures the beneficial effects of reinforcement are, in most cases, not considered. The American ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly described in the code. The...
Content type: Publications -
2012:56 Technical Note, Biosphere Dose Assessment: Review of Dose Consequence of Radionuclides in the Uranium-238 Series Decay Chain
As part of the Swedish Radiation Safety Authority (SSM) initial phase review of the Swedish Nuclear Fuel and Waste Management Company (SKB) SR-Site safety assessment for a spent nuclear fuel repository in Sweden, this technical note documents Center for Nuclear Waste Regulatory Analyses (CNWRAÒ) review of potential effects on SKB dose calculations from radioactive elements associated with...
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 -
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 -
Regulations
About the regulations in English date_desc Some of the Swedish Radiation Safety Authority’s regulations (SSMFS) are available in English. The translations are unofficial versions of the Authority’s regulations. In the event of any discrepancy between the Swedish and English versions, the Swedish original will take precedence. The Authority's regulations in Swedish...
Content type: Publications -
2012:17 Technical Note, Corrosion of copper canister
It is expected that the inflow of ground water to the deposition holes and tunnels in the Forsmark repository will be very slow. Thus, it might take some few hundred years up to thousand years before the deposition holes are filled with ground water and it might take 6000 years or more before the bentonite buffer is fully water saturated and pressurized. The copper canisters will therefore...
Content type: Publications -
2011:10e Review and evaluation of the Swedish Nuclear Fuel and Waste Management Company’s RD&D Programme 2010. Statement to the Government and summary of the review report
In accordance with Section 25 of the Ordinance (1984:14) on Nuclear Activities (Nuclear Activities Ordinance), the Swedish Radiation Safety Authority (SSM) shall review and assess the research, development and demonstration programme (RD&D programme) that the reactor licensees are obligated to establish in accordance with the Act (1984:3) on Nuclear Activities (Nuclear Activities Act).
Content type: Publications -
2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden
Marek Vasko, Vladimir Daniska, Frantisek Ondra, Peter Bezak, Kristina Kristofova, Peter Tatransky, Matej Zachar, Staffan Lindskog SKI English...
Content type: Publications