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Din avgränsning ger 573 träffar.

• 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

• 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

• 2010:47 Utveckling av programpaket för analys av termisk utmattning

  I ett tidigare NESC-projekt (Network for Evaluating Structural Components – Thermal Fatigue) togs fram en Europeisk procedur för hantering av termisk utmattning. Den tidigare myndigheten Statens kärnkraftinspektion (SKI) var en av projektets finansiärer. Proceduren innehåller bl.a. utvärdering av en modell för analys av högcykelutmattning vid turbulent termisk...

  Innehållstyp: Publikationer

• 2008:21 Sammanfattande bedömning av strålskyddet vid de kärntekniska anläggningarna i Sverige 2007

  I rapporten redovisas SSI:s bedömning av de verksamheter som bedrivits under 2007 vid de svenska kärntekniska anläggningarna. Bedömningen är ett resultat av tillsyn mot anläggningarna under året. Peter Hofvander, Lars Malmqvist, maria Lüning, Svante Ernberg, Helén Wijk, Henrik, Efraimsson, Anki Hägg, Karin Fritioff och Anders Wiebert SSI Svenska...

  Innehållstyp: Publikationer

• 2008:10 User’s manual for Ecolego Toolbox and the Discretization Block

  The CLIMB modelling team (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB’s assessment of long-term safety for a geological repository. Modelling in CLIMB covers all aspects of performance assessment (PA) from near-field releases to radiological consequences in the surface...

  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

• 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

• 2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository

  PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...

  Innehållstyp: Publikationer

• 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

• 2008:01 Myndigheternas granskning av SKB:s preliminära säkerhetsbedömningar för Forsmark och Laxemar

  Detta dokument redovisar SKI:s och SSI:s granskning av SKB:s preliminära säkerhetsbedömningar för Forsmark och Laxemar. Myndigheternas syfte med denna granskning är att bedöma om SKB:s inledande platsundersökningar har tillräcklig omfattning, håller tillräckligt hög kvalitet och omfattar de data som behövs för kommande säkerhetsanalyser.

  Innehållstyp: Publikationer