Filtered generated 755 hits.
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2017:09 Evaluation of the Swedish participation in the Nordic Nuclear Safety Research (NKS) collaboration
Background NKS is a Nordic 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 of NKS is to finance joint Nordic activities and initiatives, including seminars and workshops, technical reports, exercises and scientific articles.
Content type: Publications -
2021:19 Importance Sampling Time-Domain Random Walk (ISTIDRAW) Version 1.0 User Guide A Code for Radionuclide Transport in Pathway Networks
SSM perspective Background To support regulatory review of post-closure safety assessments of geological disposal systems it is of importance to possess regulatory independent modelling capacity. Typically, SSM’s independent modelling includes performing simple scoping calculations, utilizing the implementer’s own models with other equation solvers, or defining alternative conceptual models.
Content type: Publications -
2017:22 Effect of weld repairs on residual stresses in nickel base dissimilar metal welds
Background The driving force for crack growth near welds in nuclear application piping may arise from weld residual stresses. Experience from nondestructive examination show that cracks in dissimilar metal welds are often found near weld repairs. The repair welding may affect the residual stresses through e.g. increased tensile stresses and increased plastic straining on the surfaces of the...
Content type: Publications -
2017:05 Robust structural verification of pressurized nuclear components subjected to ratcheting, part two – stress-strain curves for cyclic elastoplastic analysis.
Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...
Content type: Publications -
2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik
Background Loss of Coolant Accidents (LOCA) are among the most demanding accidents that can happen in a Light 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. But LOCA is also an accident that the nuclear power plant is designed to...
Content type: Publications