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Din avgränsning ger 44 träffar.

• SSM Report 2008:01 A combined deterministic and probabilistic procedure for safety assessment of components with cracks – Handbook

  SSM has supported research work for the further development of a previously developed procedure/handbook (SKI Report 99:49) for assessment of detected cracks and tolerance for defect analysis. During the operative use of the handbook it was identified needs to update the deterministic part of the procedure and to introduce a new probabilistic flaw evaluation procedure. Another identified need...

  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...

  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

• 2008:07 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

• SSMFS 2008:13 Strålsäkerhetsmyndighetens föreskrifter om mekaniska anordningar i vissa kärntekniska anläggningar

  I SSMFS 2008:13 har ändringar förts in genom SSMFS 2022:5 och 2022:6.

  Innehållstyp: Publikationer

• 2008:10 International Expert Review of SR-Can: Engineered Barrier Issues

  The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...

  Innehållstyp: Publikationer

• 2008:18 Concerns when designing a safeguards approach for the back-end of the Swedish nuclear fuel cycle

  Sweden has for many years collected the spent nuclear fuel originating from nuclear power plants. This fuel must at all times be kept under supervision to render a diversion impossible; this is of course due to the possibility to make weapons from the material. One idea is to keep the nuclear material in a repository deep under the ground; this is not only to keep the material safe from theft...

  Innehållstyp: Publikationer

• 2008:11 Discrete-Feature Modelling of Groundwater Flow and Solute Transport for SR-Can Review

  Review External review contribution in support of SKI's and SSI's review of SR-Can. The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for...

  Innehållstyp: Publikationer

• 2008:47 Selected Models for Key Processes in a Nuclear Waste Repository

  The conceptual design of the disposal of spent nuclear fuel in Sweden is based on a multibarrier system. In the KBS-3 concept, the bentonite buffer is a barrier with the primary purpose of surrounding and protecting the canister. The bentonite buffer is expected to prevent or minimise the water exchange with the surrounding rock and protect the canister against mechanical damages caused by...

  Innehållstyp: Publikationer

• 2008:34 Utformning av larmsystem i svenska kärnkraftverk

  Det pågår flera stora moderniseringsprojekt inom den svenska kärnkraftindustrin. En del i dessa projekt består av att man helt eller delvis byter ut analoga informations- och manöversystem i kontrollrummen till digitala vilket förändrar larmsystemen. Digitala larmsystem har en mängd fördelar men kan också medföra risker och negativ säkerhetspåverkan.

  Innehållstyp: Publikationer