Filtered generated 763 hits.
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2017:28 SSM’s external experts’ review of SKB’s safety assessment SR-PSU - hydrogeology, geochemistry and bentonite
Background The Swedish Radiation Safety Authority (SSM) received an application for the expansion of SKB's final repository for low and intermediate level waste at Forsmark (SFR) on the 19 December 2014. SSM is tasked with the review of the application and will issue a statement to the government who will decide on the matter. An important part of the application is SKB's assessment of...
Content type: Publications -
2019:24 SSM's external experts' review of SKB's analysis of long-term safety of 1BMA (SFR)
SSM perspective Background Fractures in the concrete barrier of the rock vault 1BMA in the final repository for low and intermediate level waste (SFR) have been observed. The Swedish Radiation Safety Authority (SSM) enforced Swedish Nuclear Fuel and Waste Management Company (SKB) to assess the long-term radiological consequences of 1BMA (SSM2015-2432-26) given the present state of the rock...
Content type: Publications -
2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach
This report presents the methods and results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden, using combined boundary element (BEM) and finite element (FEM) methods The objectives of the project are: 1) to investigate the possibility of initiation...
Content type: Publications -
2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment
SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered Barrier System (EBS) and spent fuel. This workshop...
Content type: Publications -
2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister
The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...
Content type: Publications -
2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code
The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...
Content type: Publications -
2006:17 Three Dimensional Modelling of a KBS-3 Canister for Spent Nuclear Fuel some migration studies
António Pereira SKI English...
Content type: Publications -
2006:12 Geochemical Investigations of Groundwater Stability
Adrian Bath SKI English...
Content type: Publications -
2005:05 Review of SKB's Code Documentation and Testing
T.W. Hicks SKI English...
Content type: Publications