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Din avgränsning ger 302 träffar.

• 2011:34 Evolution of hydrogen by copper in ultrapure water without dissolved oxygen

  One result from this research was that the experimental difficulties of repeating Hultqvist and co-workers work are considerable and were initially underestimated. The main challenge was to obtain satisfactory tightness of all connectors involved in the experimental set-up. The problems with leakage resulted in that the research program originally planned for in this project had to be reduced...

  Innehållstyp: Publikationer

• 2010:24 On Cost Estimate for Decommissioning of one Isotope Central

  The present generation has the responsibility to ensure and guarantee that sufficient financial resources are accrued into the Swedish Nuclear Waste Fund to cover all future costs. Thus, the next generation, as well as any succeeding generations, will have the financial resources required in order to undertake the necessary measures, in an appropriate manner, for the decommissioning and...

  Innehållstyp: Publikationer

• 2010:33 Lineament interpretation Short review and methodology

  This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the author and do not necessarily coincide with those of the SSM. In the characterization of a site that may have potential for hosting a...

  Innehållstyp: Publikationer

• 2010:31 Buffer erosion: An overview of concepts and potential safety consequences

  In its safety analysis SR-Can, SKB reported preliminary results and conclusions on the mechanisms of bentonite colloid formation and stability, with a rough estimate of the consequences of loss of bentonite buffer by erosion. With the review of SR-Can the authorities (SKI and SSI) commented that erosion of the buffer had the greatest safety significance, that the understanding of the...

  Innehållstyp: Publikationer

• 2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load

  Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera värmebelastningen till en begränsad del av stavarna och därigenom öka risken...

  Innehållstyp: Publikationer

• 2013:25 Anpassning av utbildning till följd av anläggningsförändringar

  Studien baseras på dokumentstudier och intervjuer av personer inom kärnkraftindustrin men även med motsvarande roller inom flyg, petrokemi och massaindustri. De intervjuade har nyckelroller inom simulatorträningen i respektive industri. Inom kärnkraften har personer från ett verk samt från verkens gemensamma utbildningsorganisation intervjuats. De undersökta...

  Innehållstyp: Publikationer

• 2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions

  We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...

  Innehållstyp: Publikationer

• 2013:01 Validation of Weld Residual Stress Modeling in the NRC International Round Robin Study

  Weld residual stresses (WRS) have a large influence on the behavior of cracks growing under normal operation loads and on the leakage flow from a through-wall crack. Accurate prediction on weld residual stresses is important to make proper decisions when cracks in weld joints are detected. During the latest years, there has been a strong development in both analytical procedures to...

  Innehållstyp: Publikationer

• 2013:04 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 18

  The program executed in Stage 18 consists of the following three parts: Application of CoreSim with a two-dimensional model of vibrating fuel assemblies, for the calculation of ex-core detector noise throughout a fuel cycle; An investigation of the neutron noise, induced by propagating perturbations, in various thermal and fast reactor systems, in two-group theory; A consistent derivation of...

  Innehållstyp: Publikationer

• 2011:20 A Guidebook for Evaluating Organizations in the Nuclear Industry – an example of safety culture evaluation

  Organizations in the nuclear industry need to maintain an overview on their vulnerabilities and strengths with respect to safety. Systematic periodical self- assessments are necessary to achieve this overview. This guidebook provides suggestions and examples to assist power companies but also external evaluators and regulators in carrying out organizational evaluations. Organizational...

  Innehållstyp: Publikationer