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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...
Content type: Publications -
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...
Content type: Publications -
2015:27 APRI-8: Accident Phenomena of Risk Importance. En lägesrapport om forskningen inom området svåra haverier under åren 2012-2014
Kunskap om de fenomen som kan uppträda vid svåra haverier i en kärnkraftanläggning är en viktig förutsättning för att kunna förutse anläggningens beteende, för att kunna utforma rutiner och instruktioner för haverihantering, för beredskapsplaneringen samt för att få god kvalitet på haverianalyser och riskstudier. Sedan...
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 -
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 -
2015:09 PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel
Following an OCDE round robin proposal, 16 participants from 9 countries (USA, Japan, Korea (6 participants), Sweden, Germany, Czech Republic, Spain, EC and France (3 participants)) have been involved in a round robin study called PROSIR, Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel. The PROSIR project started already in 2003 and a final draft version of the main report...
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 -
2009:13e 2009 assessment of radiation safety in the Swedish nuclear power plants
This report has been prepared by order of the Swedish government in accordance with the “Governmental directive for the financial year 2009 regarding the Swedish Radiation Safety Authority”. The Swedish Radiation Safety Authority has through its supervision ensured a comprehensive basis for this overall assessment of radiation safety. The overall conclusion is that the radiation safety,...
Content type: Publications -
2008:06 Synthetic Aperture Focusing Technique in Ultrasonic Inspection of Coarse Grained Materials
Experience from the ultrasonic inspection of nuclear power plants has shown that large focused transducers are relatively effective in suppressing grain (structure) noise. Operation of a large focused transducer can be thought of as an integration (coherent summation) of individual beams reflected from the target and received by individual points at the transducer surface. Synthetic aperture...
Content type: Publications -
2007:06 Probabilistic Safety Goals - Phase 1 -Status and Experiences in Sweden and Finland
Based on a series of interviews and on literature reviews as well as on a limited interna- tional over-view, the project has described the history and current status of safety goals in Sweden and Finland. A number of issues were discussed more in detail, including the status of the safety goals in view of the fact that they are often exceeded, strategies for handling violations of safety...
Content type: Publications