Din avgränsning ger 571 träffar.
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2019:28 Avståndsberäkningar kring svenska kärnkraftverk
Underlag till hälso- och sjukvården vid planering av beredskapen för kärnkraftsolyckor i Sverige...
Innehållstyp: Publikationer -
2019:07 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Decommissioning of the Barsebäck nuclear power plant in Sweden.
Innehållstyp: Publikationer -
2012:50 Fatigue Margins for Austenitic Stainless Steels in ASME Boiler and Pressure Vessel Code – A Literature Study
Knowledge about the margins against fatigue failure in nuclear piping systems is essential. Therefore, the margins in the ASME Boiler and Pressure Vessel Code (section III) fatigue design procedure for austenitic steels, type 304/316, as applied to real components have been investigated in this literature study. It is concluded that the current knowledge about the margins in ASME for...
Innehållstyp: Publikationer -
2013:09 An Application of the Functional Resonance Analysis Method (FRAM) to Risk Assessment of Organisational Change
The objective of this study was to demonstrate an alternative approach to risk assessment of organisational changes, based on the principles of resilience engineering. The approach in question was the Functional Resonance Analysis Method (FRAM). Whereas established approaches focus on risks coming from failure or malfunctioning of components, alone or in combination, resilience engineering...
Innehållstyp: Publikationer -
2013:10s Kvalificering av elkomponenter i kärnkraftverk - Hantering av åldring
Syftet med arbetet har varit att skapa ett underlag att användas vid planering av arbetet med miljökvalificering av framför allt komponenter i inneslutningen. Principerna är även tillämpbara utanför inneslutningen i områden som kommer att utsättas för ökad miljöpåkänning i samband med olika händelser. Rapporten är...
Innehållstyp: Publikationer -
2014:01 Cost Estimating for Decommissioning Nuclear Reactors in Sweden
In Sweden, decommissioning cost estimates are core inputs to the process of calculating licensee contributions to the Swedish national fund for radioactive waste management and decommissioning. Under the present system, the decommissioning cost estimates are produced by licensees every three years and formally submitted to the Swedish Radiation Safety Authority (SSM), which reviews the...
Innehållstyp: Publikationer -
2014:27 Regulation applying to welding of pressure equipment – a comparative study
The PED was in force in November 1999 and has been mandatory in European Union Member States since May 2002. Most of the standards referred to in the PED are relatively new although some of the standards were adopted in the early 1990s. On the other hand, the ASME B&PV Code has been used for a long time now and is the result of several decades of industrial experiences. The authors present...
Innehållstyp: Publikationer -
2012:70 Process Parameters Affecting Inhomogeneity of Material Microstructure
There’s been a tremendous change in the number, product types, locations, equipment, and manufacturing capabilities of stainless steel producers from the late 1960’s to present. This reconfiguration of the global steel industry occurred between the early 1970’s to the mid 1980’s and continues today. These changes have produced a loss in manufacturing flexibility, due to the inherent...
Innehållstyp: Publikationer -
2014:28 Numerical simulation of ductile crack growth in residual stress fields
The study has shown on the capability of the cell model in capturing the effects on ductile tearing from limited pre-load levels and a residual stress field. Some of the conclusions are as follows: No distinctive influence on the material fracture toughness is observed from pre-loading (work hardening), both tensile and compressive, at room temperature of 1.5 or 3 % total strain. The cell...
Innehållstyp: Publikationer -
2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4
The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...
Innehållstyp: Publikationer