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Din avgränsning ger 400 träffar.

• 2012:58 Technical Note, Independent radionuclide transport modelling – Reproducing results for main scenarios

  referred to simply as the “Radionuclide Transport Report.” The modelling focused on two scenarios: (i) Canister Failure by Corrosion and (ii) Canister Failure by Shear Load, to evaluate whether SKB computations ... support the safety assessment documented in the SR-Site main report (SKB, 2011). The review evaluated (i) transparency of the SKB computations (e.g., are data and descriptions sufficient to reproduce computations...

  Innehållstyp: Publikationer

• 2014:29 Technical Note, Independent Modelling of Radionuclide Transport, Evaluation of Colloid Transport Modelling – Main Review Phase

  case. Modelling radionuclide attachment to clay colloids as reversible linear equilibrium sorption (i.e., using a Kd distribution factor approach) is reasonable and well supported. Nonetheless, in this ... case.  Modelling radionuclide attachment to clay colloids as reversible linear equilibrium sorption (i.e., using a Kd distribution factor approach) is reasonable and well supported.  Nonetheless, in this...

  Innehållstyp: Publikationer

• 2009:06 Bonussystem och dess inverkan på säkerheten: en intervjubaserad pilotstudie vid de svenska kärnkraftverken

  beteende och de risker som här kan finnas. För att skapa en tolkningsram granskades belöningars relevans i ljuset av dels ett brett spektrum av teorier om motivation, dels empiri rörande belöningars effekter ... beteende och de risker som här kan finnas. För att skapa en tolkningsram granskades belöningars relevans i ljuset av dels ett brett spektrum av teorier om motivation, dels empiri rörande belöningars effekter...

  Innehållstyp: Publikationer

• 02:4 Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing

  work was finished and reported in Swedish in a limited publication 2000, Ingemansson Rapport H-14061-r-I. As the performed work was regarded to be of more general interest it is published again as a research ... work was finished and reported in Swedish in a limited publication 2000, Ingemansson Rapport H-14061-r-I. As the performed work was regarded to be of more general interest it is published again as a research...

  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

  future safety assessments. To foster a dialogue with the authorities that oversee SKB’s activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI ... future safety assessments. To foster a dialogue with the authorities that oversee SKB’s activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI...

  Innehållstyp: Publikationer

• 2012:24 Technical Note, Initial Review of SR-Site Main Report

  complete in the sense that it includes all of the expected assessment steps. SR-Site suggests that (i) buffer erosion and copper corrosion leading to canister failure, and (ii) canister failure due to shear ... complete in the sense that it includes all of the expected assessment steps.  SR-Site suggests that (i) buffer erosion and copper corrosion leading to canister failure, and (ii) canister failure due to shear...

  Innehållstyp: Publikationer

• 2001:23 Interactions of Severe Accident Researchand Regulatory Positions (ISARRP)

  This project, started on April 1, 1999, had the specific objectives of determining whether; (i) the focus of the severe accidents (SA) research is consistent with that of the regulatory authorities, (ii) ... English This project, started on April 1, 1999, had the specific objectives of determining whether; (i) the focus of the severe accidents (SA) research is consistent with that of the regulatory authorities...

  Innehållstyp: Publikationer

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

  observations. It also provides a comparison of different codes used in fracture prediction during the NESC-I test. Some important conclusions and recommendations for each of these projects can be found at the ... observations. It also provides a comparison of different codes used in fracture prediction during the NESC-I test. Some important conclusions and recommendations for each of these projects can be found at the...

  Innehållstyp: Publikationer

• 2009:07 Dependency Analysis Guidance Nordic/German Working Group on Common Cause Failure analysis

  VGB, with the aim to create a common experience base for defence and analysis of dependent failures i.e. Common Cause Failures CCF. Phase 2 in this project if a deepen data analyses of CCF events and a ... VGB, with the aim to create a common experience base for defence and analysis of dependent failures i.e. Common Cause Failures CCF. Phase 2 in this project if a deepen data analyses of CCF events and a...

  Innehållstyp: Publikationer

• 2013:08 Licensing of safety critical software for nuclear reactors

  accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying ... cases and demonstrations of safety of software based systems; as guidance for manufacturers and major I&C suppliers on the international market. The SSM report 2013:08 has been updated with a new revision...

  Innehållstyp: Publikationer