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Din avgränsning ger 571 träffar.

• SSMFS 2018:4 Strålsäkerhetsmyndighetens föreskrifter om naturligt förekommande radioaktivt material och byggnadsmaterial

  SSMFS 2018:4 har upphävt SSMFS 2011:4. Ändringsföreskrift SSMFS 2019:2 och senare SSMFS 2019:5 har ändrat övergångsbestämmelsen till 7 § i SSMFS 2018:4.

  Innehållstyp: Publikationer

• 2018:19 Licensing of safety critical software for nuclear reactors

  Common position of international nuclear regulators and authorised technical support organisations – Revision 2018...

  Innehållstyp: Publikationer

• 1997:05 SKI SITE-94

  The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...

  Innehållstyp: Publikationer

• 96:41 SKIs utvärdering av SKBs FUD-program 95

  Sammanställning av remissvar...

  Innehållstyp: Publikationer

• 96:49 SKIs utvärdering av SKBs FUD-program 95

  Sammanfattning och slutsatser...

  Innehållstyp: Publikationer

• 96:48 SKIs utvärdering av SKBs FUD-program 95

  Gransknings-PM...

  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

• 2019:16 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU

  – consequence analysis and hydrogeological aspects Main review phase...

  Innehållstyp: Publikationer