Filtered generated 401 hits.
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2015:18 Uranium Aerosol Characteristics at a Nuclear Fuel Manufacturing Site - Particle Size, Morphology and Chemical Composition
Vid alla kärntekniska verksamheter krävs att strålningsmiljön kontrolleras dels genom mätningar av ytors- och luftens kontamination i anläggningen och dels med persondosimetriverksamhet inkluderat helkroppsmätning. De olika metoder som används för att beräkna intecknad effektiv stråldos från kontinuerligt intag via inandning är förknippade...
Content type: Publications -
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...
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 -
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 -
2015:09 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 -
2009:15 Improvement and Validation of Weld Residual Stress Modelling Procedure
Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...
Content type: Publications -
2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA
No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...
Content type: Publications -
2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3
In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...
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 -
2009:27 Analysis Strategy for Fracture Assessment of Defects in Ductile Materials
SSM has supported research for investigating the role of secondary stresses when fracture assessments are performed for cracked structures made of ductile materials. There are evidences that indicate that some secondary stresses, such as weld residual stresses, are not as important as primary stresses for estimating the safety margin against rupture (measured by the J-integral) for the type...
Content type: Publications