Filtered generated 759 hits.
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2022:03 Effect of Neutron Irradiation on the Oxidation and Corrosion of Austenitic Stainless Steels
SSM perspective Background Reactor pressure vessel internal components of austenitic stainless steel located close to the core are subject to a high neutron flux. Irradiation by fast neutrons induces changes in the material that affect microstructure, mechanical properties and microchemistry. These changes eventually lead to an increased susceptibility to irradiation assisted stress corrosion...
Content type: Publications -
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 -
2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents
In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors. The objective is to assess if the inertia effects are important enough to warrant modification of QT-COOL, a coolant channel module for two-phase flow that has recently been implemented as...
Content type: Publications -
01:2024 01:2024 Overview of radon management in the Nordic countries
Report from working group Nordic-Nat...
Content type: Publications -
03:2024 Radon dose conversion coefficients and their use in the Nordic countries
Report, Nordic-Nat...
Content type: Publications -
SSMFS 2008:1 The Swedish Radiation Safety Authority’s Regulations concerning Safety in Nuclear Facilities
SSMFS 2010:3 is only available in Swedish. The latest consolidated version of the regulation with amendments made up to and including SSMFS 2018:12 is only available in Swedish. SSM English SSMFS 2010:3 is only available in Swedish. The latest consolidated version of the regulation with amendments made up to and including SSMFS 2018:12 is only available in Swedish.
Content type: Publications