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Din avgränsning ger 302 träffar.

• 2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C

  The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...

  Innehållstyp: Publikationer

• 2010:24 On Cost Estimate for Decommissioning of one Isotope Central

  The present generation has the responsibility to ensure and guarantee that sufficient financial resources are accrued into the Swedish Nuclear Waste Fund to cover all future costs. Thus, the next generation, as well as any succeeding generations, will have the financial resources required in order to undertake the necessary measures, in an appropriate manner, for the decommissioning and...

  Innehållstyp: Publikationer

• 2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark

  SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...

  Innehållstyp: Publikationer

• 2010:18 Radionuclide Transport: Preparation During 2009 for the SR-Site Review

  Post-closure safety assessments for nuclear waste repositories involve radioecological modelling for an underground source term. Following several decades of research and development, the Swedish Nuclear Waste Management Company (SKB) is approaching a phase of license application. According to SKB’s plans, an application to construct a geological repository will be submitted by the end of...

  Innehållstyp: Publikationer

• 2009:35 Evaluation of SKB/Posiva’s report on the horizontal alternative of the KBS-3 method

  The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. The method has two design alternatives: the vertical (KBS-3V) and the horizontal (KBS-3H). SKB and Posiva have conducted a joint research, development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a...

  Innehållstyp: Publikationer

• 2010:31 Buffer erosion: An overview of concepts and potential safety consequences

  In its safety analysis SR-Can, SKB reported preliminary results and conclusions on the mechanisms of bentonite colloid formation and stability, with a rough estimate of the consequences of loss of bentonite buffer by erosion. With the review of SR-Can the authorities (SKI and SSI) commented that erosion of the buffer had the greatest safety significance, that the understanding of the...

  Innehållstyp: Publikationer

• 2019:25 Maskulinitet, risk och säkerhet vid ett svenskt kärnkraftverk

  SSM perspektiv Bakgrund Likt anställda vid ett järnverk, ett pappersbruk eller en oljeplattform omges även personalen vid ett kärnkraftverk av olika slags risker som hanteras genom ett mer eller mindre lyckosamt säkerhetsarbete. Kärnkraften är en högriskbransch och riskerna för de personer som arbetar inom den har inte enbart med reaktorn och den radioaktiva...

  Innehållstyp: Publikationer

• 2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study

  SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high primary loads. The Swedish procedure for safety assessment of components with defects is documented in...

  Innehållstyp: Publikationer

• 2019:01 Research within technical safeguard at Uppsala university during 2016-20

  Summary Uppsala University has since January 2016 undertaken an extensive research programme in technical nuclear safeguards within the framework of contract SSM2016-661, including in total 3 PhD students and 7 senior researchers. This report marks the final reporting covered by this contract. The executed research covers the following projects; (1) Methodologies for safeguards assessment of...

  Innehållstyp: Publikationer

• 2008:12 Independent Calculations for the SRCan Assessment

  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