Din avgränsning ger 43 träffar.
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2015:07 TEM-lamella lift-out from the crack tip region of Alloy 600 for high resolution electron microscopy examination
contributes to the development of a method for high-quality TEM lamella preparation from crack tip regions of nuclear materials. A standard compact tension (CT) specimen of Alloy 600 previously tested for ... corrosion crack growth in simulated PWR primary water was used to demonstrate the benefit of the proposed method. This report describes the procedure for cutting the CT specimen in order to access the crack...
Innehållstyp: Publikationer -
2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting
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 ... ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material models currently used for structural verification of pressurized nuclear components...
Innehållstyp: Publikationer -
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, ... application of SKB to build such a final disposal facility. The biosphere dose assessment carried out as part of SR-Site features a highly detailed model of the evolution of the landscape in Forsmark area...
Innehållstyp: Publikationer -
2015:32 Safe and responsible management of spent nuclear fuel and radioactive waste in Sweden - National Plan
The National Plan describes the general principles (national policies), the legislative, regulatory and organizational framework (national framework) as well as the strategies (national ... strategies (national programme and systems) that control the safe and responsible management of spent nuclear fuel and of all types of radioactive waste in Sweden, now and in the future. Flavio Lanaro (project...
Innehållstyp: Publikationer -
2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects
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 ... definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the understanding of safety culture challenges facing regulators and power companies in different...
Innehållstyp: Publikationer -
2015:05 Technical Note, Review of uncertainty propagation and sensitivity analysis in SR-Site Main Review Phase
SSM2014-2060 “Review of uncertainty and sensi- tivity analysis in SR-Site” addressed three issues: Adequacy of the methods adopted by SKB for conducting sensitivity analyses Approach for use of conservative and ... Propagation of uncertainty for the corrosion scenario Adequacy of the methods for sensitivity analyses: The sensitivity analyses (SA) were carried out using well-established approaches the choice of which is...
Innehållstyp: Publikationer -
2015:41 Technical Note, Hydrogeological aspects of future human actions for a repository at Forsmark
Joel E. Geier SSM English...
Innehållstyp: Publikationer -
2015:50 Assessment of structures subject to concrete pathologies (ASCET)
Nuclear Power Plants around the world are at the moment approaching, or in, their Long Term Operation stage of their operational phase. In addition, several NPPs have recently been carrying out uprate and life ... exchange of components important to safety, in order to extend their lifetime. As a result, ageing management has emerged as one of the main concerns of the nuclear community. The ASCET (Assessment of Nuclear...
Innehållstyp: Publikationer -
2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Ali R. Massih, Lars Olof Jernkvist SSM English...
Innehållstyp: Publikationer -
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 ... Hutchinson to evaluate its capability in predicting the effect of residual stresses. Experimental work has also been conducted for material characterization. The material used in the experiments was A533B-1. The...
Innehållstyp: Publikationer
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