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  • 2008:17 Review of SR-Can: Evaluation of SKB’s handling of spent fuel performance, radionuclide chemistry and geosphere transport parameters

    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 spent nuclear...

    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
  • 2008:23 SKI’s and SSI’s review of SKB’s safety report SR-Can

    This report summarises the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) joint review of the Swedish Nuclear Fuel & Waste Management Co’s (SKB) safety report SR-Can, on post-closure safety for a KBS-3 spent nuclear fuel repository at Forsmark and Laxemar respectively (SKB TR-06-09). As of 1 July 2008 the Swedish Radiation Safety...

    Innehållstyp: Publikationer
  • 2008:16 Review of SKB:s Safety Assessment SR-Can: Contributions in Support of SKI:s and SSI:s Review by External Consultants

    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 spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety...

    Innehållstyp: Publikationer
  • 2016:25 Licensing of safety critical software for nuclear reactors

    – Common position of international nuclear regulators and authorised technical support organisations – Revision 2015...

    Innehållstyp: Publikationer
  • 2016:35 Säkerhetsvärdering mot plastisk kollaps vid skadetålighetsanalyser

    Bakgrund Proceduren som används för brottmekanisk analys av defekter och inspektionsintervall för komponenter i svenska kärntekniska anläggningar utgår från den brittiska R6-metoden men är vidareutvecklad för att ha ett säkerhetsvärderingssystem som är kompatibelt med säkerhetskraven som uttrycks i den amerikanska tryckkärlsstandarden...

    Innehållstyp: Publikationer
  • 2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014

    This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...

    Innehållstyp: Publikationer
  • 2016:39 Recommended residual stress profiles for stainless steel pipe welds

    Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations of weld residual stress (WRS) distributions. Detailed knowledge of the residual stress field in different types of welds is important since they can have substantial influence on...

    Innehållstyp: Publikationer
  • 2015:44 Krav på funktion, konstruktion och provning av reaktorinneslutningar

    Bakgrund I Sverige behöver SSM skaffa vidare kunskap inom olika områden inom nukleära byggnadskonstruktioner bl.a. reaktorinneslutningar. Syfte Syftet med projektet "Krav på funktion, konstruktion och provning av reaktorinneslutningar" är att sammanställa information för att belysa viktiga reaktorinneslutningsfrågor vid byggnation. Den sammanställda...

    Innehållstyp: Publikationer