Filtered generated 374 hits.
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2009:07 Dependency Analysis Guidance Nordic/German Working Group on Common Cause Failure analysis
The Regulatory Code SSMFS 2008:1 of Swedish Radiation Safety Authority (SSM) includes requirements regarding the performance of probabilistic safety assessments (PSA), as well as PSA activities in general. Therefore, the follow-up of these activities is part of the inspection tasks of SSM. According to the SSMFS 2008:1, the safety analyses shall be based on a systematic identification and...
Content type: Publications -
2007:25 Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach
The study used the themes identified in an earlier study: definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reminders on different aspects of safety management in the nuclear context. reporting, and measurement of...
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 -
2006:15e Safety and Radiation Protection at Swedish Nuclear Power Plants 2005
The safety philosophy upon which the Swedish Nuclear Power Inspectorate’s (SKI) supervisory and regulatory activities are based assume that multiple physical barriers will exist and that a plant-specific defence-in-depth system will be implemented at each plant and that the licensee bears the undivided responsibility for safety. The physical barriers are situated between the radioactive...
Content type: Publications -
2007:41 Dependency Analysis Guidence, Nordic/German Working Group on Common cause Failure analysis Phaase 1 project report: Comparison and application to test cases
The report “Nordic/German Working Group on Common cause Failure analysis. Phase 1 project report: Comparisons and application to test cases” presents a common attempt by the authorities and the utilities to create a methodology and experience base for defence and analysis of dependent failures. The performed benchmark application has shown that how the data is interpreted is of significant...
Content type: Publications -
2014:32 Technical Note, Assessment of the derivation and use of distribution coefficients and concentration ratios – Main Review Phase
This report presents a review of the approaches and databases which SKB have used to derive concentration ratios (CRs) and distribution coefficients (Kds) to consider if they are robustly derived and fit for purpose. Credible alternative approaches are also considered. The focus of this review are SKB reports R-10-28 and TR-10-07 which describe the available site specific data and the...
Content type: Publications -
2015:29 Technical Note, Quality Assurance in SKB’s Copper Corrosion Experiments
I Sverige planeras slutförvaring av använt kärnbränsle. Metoden som har utvecklats kallas för KBS-3 och den bygger på tre skyddsbarriärer; kopparkapslar, bentonitlera och det svenska urberget. Det specifika syftet med den här rapporten är att få en förståelse för, och en bedömning av, SKB:s kvalitetssäkring av deras försök...
Content type: Publications -
2012:18 Technical Note, SR-Site Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Contribution to the Initial Review Phase
This review has focussed mainly on the modelling of the Engineered Barrier System (EBS) evolution, which includes coupled thermal, hydraulic, mechanical and chemical (THMC) processes. Additionally, the role of the EBS in the wider safety case was reviewed, including its treatment in scenarios and its representation in conceptual models since this provided the motivation for the modelling work...
Content type: Publications -
2012:34 Technical Note, Review of FEP Handling in the SR-Site Safety Assessment: Initial Review Phase
On 16th March 2011 the Swedish Nuclear Fuel and Waste Management Company, SKB, submitted applications for licences to construct a spent nuclear fuel encapsulation facility in Oskarshamn and a repository for final disposal of the encapsulated fuel in Forsmark. SKB’s applications are currently being reviewed by the Swedish Radiation Safety Authority, SSM, and the Land and Environmental Court in...
Content type: Publications -
2012:37 Technical Note, Selective review of the hydrogeological aspects of SR-Site
This review of the hydrogeology is selective. It focuses on the measurement, interpretation and modelling of the potential repository host rock, that is the rock domain FFM01<-400m. It accepts as reasonably accurate the measurement and representation of the more transmissive parts of the hydrogeological system, particularly the near-surface 150m in the form presented by SKB. SKB have decided...
Content type: Publications