Showing 594
-
2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2
only be understood by a combination of testing and numerical simulations. As concrete is a complex material, interaction between anchors, reinforcement and concrete is consequently also complex. Reported ... Inspecta Nuclear AB and Scanscot Technology AB have, in a previous work funded by SSM (SSM 2013: 27), studied the possibility to transfer mechanical loads from embedded anchors to the concrete and its reinforcement...
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 ... into granitic rock. After emplacement of the canisters Bentonite swelling due to water saturation and hydrostatic pressure build up the canisters will be subjected to compressive loads. The canisters are...
Content type: Publications -
2017:16 Stress intensity factor solutions for circumferential cracks in cylindrical bars under axisymmetric loading and global bending
ProSACC code. The need for such a geometry, especially considering nonlinear axisymmetric loading and global bending, has motivated the development of new stress intensity factor solutions, also known ... for example due to thermal fatigue loadings. This means that both nonlinear axisymmetric loading and global bending loads have to be taken into account. Results The K-solutions, which have been numerically...
Content type: Publications -
2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method ... method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish Radiation...
Content type: Publications -
2017:13 Monte Carlo patient-specific pre-treatment QA system for volumetric modulated arc therapy
point dose verification and/or dose distribution verification performed in a homogenous phantom. One drawback is the difficulty to interpret deviations between predicted and measured doses, if the deviation ... distributions. Another weakness is that the recalculations are performed for a homogenous phantom and not for the real patient. Furthermore, there are a resolution limitations caused by the distance between...
Content type: Publications -
2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik
Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subsequent release of active material ... the fragementation of pellets and axial relocation of fuel fragments. Fuel fragments that move within the rod can accumulate at positions where the cladding is strained and cause an increased load there...
Content type: Publications -
2017:11 Extended Common Load Model: A tool for dependent failure modelling in highly redundant structures
Background The treatment of dependent failures is one of the most controversial subjects in reliability and risk analyses. The difficulties are specially underlined in the case of highly redundant systems, when ... group (NPSAG) including SSM. It has therefore been an interest to have the method properly documented and published. The objective with this report is to describe the mathematical details in the definition...
Content type: Publications -
2017:09 Evaluation of the Swedish participation in the Nordic Nuclear Safety Research (NKS) collaboration
promoting cooperation on nuclear safety and emergency preparedness research. The research program is primarily funded by Nordic radiation safety authorities and responsible ministries. The main purpose ... joint Nordic activities and initiatives, including seminars and workshops, technical reports, exercises and scientific articles. Both radiation safety authorities, industries and research actors are engaged...
Content type: Publications -
2017:05 Robust structural verification of pressurized nuclear components subjected to ratcheting, part two – stress-strain curves for cyclic elastoplastic analysis.
exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material models currently used for structural verification of pressurized ... guidelines on how to evaluate pressurized nuclear components subjected to ratcheting in a rational and conservative way that are code compliant with ASME III. In part one (SSM 2015:43) experimental studies...
Content type: Publications -
2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C
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 ... present SSRT experiments the objective were to identify if thresholds in regards to tensile stress and sulfide concentration under which SCC does not occur in the designed experiment could be identified...
Content type: Publications