Filtered generated 276 hits.
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2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Ali R. Massih, Lars Olof Jernkvist SSM English...
Content type: Publications -
96:51 The Flooding Incident at the Ågesta Pressurized Heavy Water Nuclear Power Plant
This report is a Master's thesis in Nuclear Reactor Engineering to be submitted to the SKi (Swedish Nuclear Power Inspectorate). The work has been performed at the Division of Nuclear Power Safety, KTH,Stockholm. It is an independent investigation of the consequences of the flooding incident at the Agesta HPWR, in Stockholm, Sweden, which occurred on the 1st of May 1969. The issue was raised...
Content type: Publications -
1992:3 Characterization of seismic ground motions for probabilistic safety analyses of nuclear facilities in Sweden. SUMMARY REPORT
In Scandinavia seismic activity is generally low. Only a few incidents have been registered in historic time, which might have damaged an industrial plant of today. The risk of a nuclear accident in Sweden, caused by an earthquake, may thus be considered to be low. The two latest reactors Forsmark 3 and Oskarshamn 3 have been analysed and designed to resist a specified earthquake. For the...
Content type: Publications -
2016:28 Fatigue fracture surface characterization and investigation
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to examine the obtained fatigue cracks with an optical microscope. Objective The present study performs a fractographical examination of the obtained fatigue cracks with the aim of determine where...
Content type: Publications -
2016:26 Ensemble for deterministic sampling with positive weights
The aim of this project is to find a reliable method for determining an ensemble for Deterministic Sampling with only positive weights. This report is intended to work as a presentation of the project, as well as to work as a beginner’s guide to DS. In the report several methods for generating DS ensembles are presented, which can encode up to four moments and represent any kind of...
Content type: Publications -
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...
Content type: Publications -
2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads
Cracked components are usually subjected to loads causing both primary and secondary stresses, e.g. welding components. Engineering assessment approaches, such as the ASME XI code and the R6 procedure, are commonly used to conduct integrity assessment of such components. There has been an ongoing debate how to treat secondary stresses using engineering assessment methods. The nature of these...
Content type: Publications -
2015:04 DiD-PSA: Development of a Framework for Evaluation of the Defence-in-Depth with PSA
The project declares an interpretation of the definitions of Defence in Depth given by IAEA which outline a framework to meet PSA. For each level of defence and combinations of levels, methods to give estimates from a PSA perspective are presented and discussed. One important result is the discussion of the basic definitions and the basis for defence-in-depth, as defined by IAEA, leading to...
Content type: Publications -
2011:29 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 17
This report constitutes Stage 17 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 16 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.
Content type: Publications -
2014:09 Further Development of the Core Simulator CORE SIM: Extension to coupled capabilities for BWRs
The developed tool is fully MatLab based and requires a set of input data from a commercial static core simulator. The driving perturbation can be specified both as a perturbation in thermo-hydraulic parameters or directly as a perturbation in macroscopic cross-sections. As output, the 3-dimensional spatial distribution of the noise in coolant density, pressure, enthalpy, inlet velocity, fuel...
Content type: Publications