Filtered generated 31 hits.
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2015:11 Investigation of the Distribution of Phosphorus in Copper
Two copper alloys containing different amounts of phosphorus, 6 and 80 wtppm, respectively, have been investigated. The matrix of both alloys was analysed using atom probe tomography (APT). The matrix P concentration in the 80 wtppm P mate- rial was about the same as the bulk concentration and it was therefore concluded that the majority of the P atoms resides in the matrix. Grain boundaries...
Content type: Publications -
2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting
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 -
2015:53 Ductile tearing – Micromechanical analyses and experimental study
In this report, the project "Ductile Tearing-Micromechanical analyses and experimental study" is presented. In the project, numerical cell modeling has been conducted using the shear modified Gurson model proposed by Nahshon and Hutchinson to evaluate its capability in predicting the effect of residual stresses. Experimental work has also been conducted for material characterization.
Content type: Publications -
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...
Content type: Publications -
2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects
Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...
Content type: Publications -
2015:20 The effects of mild, acute hypoxia on cognitive performance
Room air with reduced oxygen levels that prevent materials to ignite and combust is a cost-effective and increasingly popular fire prevention method. For system safety reasons, the effects of hypoxia, that is, the lack of sufficient oxygen (that is, less than 21% oxygen which is the approximate oxygen level of normal air), on cognitive performance of persons working under such conditions are...
Content type: Publications -
2015:47 GEMA-Site 1: Model description and example application
Background In 2011 the Swedish Nuclear Fuel and Waste Management Company (SKB) submitted an assessment of the long-term safety of a KBS-3 geological disposal facility for spent nuclear fuel in Forsmark, Sweden. This assessment, the SR-Site project, supports the licence application of SKB to build such a final disposal facility. The biosphere dose assessment carried out as part of SR-Site...
Content type: Publications -
2015:06 Technical Note, Feasibility of Backfilling Deposition Tunnels
SKB has been conducting an appropriate scientific and technical programme of research and development work to investigate the many processes that may affect the choice of backfill materials, the practicali- ties of backfill emplacement, and the properties of the emplaced backfill that may affect long-term radiological safety. On the basis of this re- search and development work SKB has outlined...
Content type: Publications -
2015:05 Technical Note, Review of uncertainty propagation and sensitivity analysis in SR-Site Main Review Phase
The review assignment SSM2014-2060 “Review of uncertainty and sensi- tivity analysis in SR-Site” addressed three issues: 1. Adequacy of the methods adopted by SKB for conducting sensitivity analyses 2. Approach for use of conservative and best-estimate parameter values 3. Propagation of uncertainty for the corrosion scenario Adequacy of the methods for sensitivity analyses: The sensitivity...
Content type: Publications -
2015:01 Technical Note, Rock Mechanics - Thermal properties and thermal modelling of the rock in a repository of spent nuclear fuel at Forsmark – Main Review Phase
In preparation for the review of SKB's license application for a disposal of spent nuclear fuel, SSM has conducted a series of modelling studies related to the design, construction and long-term safety of a repository at Forsmark. Several of the presented modelling works are related to the thermal evolution of the repository with time. This report extracts the results from independent SSM...
Content type: Publications