Din avgränsning ger 239 träffar.
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2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility
Background For final storage of spent nuclear fuel it is suggested by the Swedish nuclear fuel and waste management company (SKB) to emplace the nuclear fuel into copper canisters which are surrounded by bentonite clay at approximately 500 meters’ depth into granitic rock. After emplacement of the canisters Bentonite swelling due to water saturation and hydrostatic pressure build up the...
Innehållstyp: Publikationer -
2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C
Background Stress corrosion cracking (SCC) can occur in materials from the combined influence of tensile stress and a corrosive environment. It has previously been shown in the literature, that copper can be sensitive to SCC in the presence of sulfide containing water. Since both tensile...
Innehållstyp: Publikationer -
2017:28 SSM’s external experts’ review of SKB’s safety assessment SR-PSU - hydrogeology, geochemistry and bentonite
Main review phase...
Innehållstyp: Publikationer -
2014:35 Technical Note, Modelling comparison of alternative biosphere models with LDF models and evaluation of selected parameter values used in the biosphere dose assessment - Main review phase
This report has been prepared as part of the SSM’s Main Review Phase of SKB’s SR-Site performance assessment of the long-term safety of the KBS-3 geological disposal facility (GDF) proposed for construction at Forsmark. The review addresses the methodology employed in the dose assessment calculations of SR-Site; specifically issues of transport, accumulation and transfers of radionuclides in...
Innehållstyp: Publikationer -
2014:40 Technical Note, Review of Performance Confirmation Programs and Potential Roles in SSM’s Current Review of SKB’s License Application – Main Review Phase
The initial license application of a repository concept for disposal of radioactive waste is based on extensive site characterization, baseline monitoring, development of disposal designs and engineered barriers, test data on engineered barriers, and the integration of a series of models representing processes controlling the containment, release and migration of radionuclides from the...
Innehållstyp: Publikationer -
2014:11 Technical Note, Radionuclide Solubility Limits in SKB’s Safety Case
The Swedish Radiation Safety Authority (SSM) is reviewing a license application, which has been submitted by Svensk Kärnbränslehantering AB (SKB), for a spent nuclear fuel repository at Forsmark. This technical note records the findings from a project that forms part of the main phase of SSM’s license application review. The project involved review of reports and independent modelling...
Innehållstyp: Publikationer -
2014:10 Technical Note, Rock Mechanics - Confidence of SKB’s models for predicting the occurrence of spalling – Main Review Phase
This review study is placed in the context of SSM’s Main Review Phase for SKB’s safety assessment SR-Site. The assignment is titled “Rock Mechanics – Confidence of SKB’s models for predicting the occurrence of spalling”. The report presents the authors’ assessment in response to the questions raised by SSM. The review concentrated on two main issues: (1) the analysis of the assumptions made...
Innehållstyp: Publikationer -
2014:32 Technical Note, Assessment of the derivation and use of distribution coefficients and concentration ratios – Main Review Phase
This report presents a review of the approaches and databases which SKB have used to derive concentration ratios (CRs) and distribution coefficients (Kds) to consider if they are robustly derived and fit for purpose. Credible alternative approaches are also considered. The focus of this review are SKB reports R-10-28 and TR-10-07 which describe the available site specific data and the...
Innehållstyp: Publikationer -
2014:29 Technical Note, Independent Modelling of Radionuclide Transport, Evaluation of Colloid Transport Modelling – Main Review Phase
SKB excludes consideration of colloids originating inside the canister in its performance assessment on the basis of the filtration capability of the buffer material. In the canister failure by corrosion scenario (central corrosion case), the buffer material is assumed eroded, and the filtration argument is not entirely valid for excluding modelling in-canister colloids. In this Technical...
Innehållstyp: Publikationer -
2014:34 Technical Note, Modelling Comparison of Simple Reference Biosphere Models with LDF Models – Main Review Phase
This Technical Note describes the development of simple reference biosphere models as a means of exploring the Landscape Dose Factor (LDF) approach adopted by SKB in the SR-Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site. The models are developed and described in a systematic manner, based on international guidance reflected in the...
Innehållstyp: Publikationer