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Din avgränsning ger 302 träffar.

• 2008:05 International Expert Review of SR-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can

  In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The report represented the culmination of work conducted by SKB over several years, focusing on the goal of making the licence application in late 2009. Results from the SR-Can project have been documented in several...

  Innehållstyp: Publikationer

• 2008:08 SSI:s independent consequence calculations in support of the regulatory review of the SR-Can safety assessment

  With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can project demonstrates progress in SKB’s capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to...

  Innehållstyp: Publikationer

• 2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment

  An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...

  Innehållstyp: Publikationer

• SSMFS 2008:3 Strålsäkerhetsmyndighetens föreskrifter och allmänna råd om kontroll av kärnämne mm

  Du kan ladda ner eller beställa Strålsäkerhetsmyndighetens föreskrifter och allmänna råd (SSMFS 2008:3) om kontroll av kärnämne mm, se nedan. Vid beställning av den här föreskriften får du den konsoliderade versionen skickad till dig. Konsoliderad version är en version av föreskrifterna där alla ändringar har förts...

  Innehållstyp: Publikationer

• 2011:06 Reliability Data Handbook for Piping Components in Nordic Nuclear Power Plants – R Book, Phase 2

  The Nordic PSA Group (NPSAG) has undertaken to develop a piping reliability parameter handbook for use in risk-informed applications that involve the consideration of structural integrity of piping systems. The scope of the handbook is to establish high quality reliability parameters that account for the Nordic and worldwide service experience with safety-related and non-safety-related piping...

  Innehållstyp: Publikationer

• 2010:36 Guidance for the Definition and Application of Probabilistic Safety Criteria

  Safety goals are defined in different ways in different countries and also used differently. Many countries are presently developing them in connection to the transfer to risk-informed regulation of both operating nuclear power plants (NPP) and new designs. However, it is far from self-evident how probabilistic safety criteria should be defined and used. On one hand, experience indicates that...

  Innehållstyp: Publikationer

• 2011:05 Overview and Evaluation of the NESC Projects for Fracture Assessments of Nuclear Components

  The Network for Evaluation of Structural Components (NESC) was started in 1993 and since then six different projects have been carried out. A seventh NESC-project is still in progress. The overall objective of these projects has been to study the reliability of the entire process of structural integrity assessment within an international framework. The network is coordinated by the European...

  Innehållstyp: Publikationer

• 2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components

  During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of...

  Innehållstyp: Publikationer

• 2019:25 Maskulinitet, risk och säkerhet vid ett svenskt kärnkraftverk

  SSM perspektiv Bakgrund Likt anställda vid ett järnverk, ett pappersbruk eller en oljeplattform omges även personalen vid ett kärnkraftverk av olika slags risker som hanteras genom ett mer eller mindre lyckosamt säkerhetsarbete. Kärnkraften är en högriskbransch och riskerna för de personer som arbetar inom den har inte enbart med reaktorn och den radioaktiva...

  Innehållstyp: Publikationer

• 2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study

  SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high primary loads. The Swedish procedure for safety assessment of components with defects is documented in...

  Innehållstyp: Publikationer