Din avgränsning ger 571 träffar.
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2012:54 Technical Note, Initial Review Phase for SKB´s safety assessment SR-Site: Geological structures and deformation zones, from site investigation to safety assessment
The site selected by the Swedish Nuclear Fuel and Management Co (SKB) for location of a deep geological repository, i.e. a storage for spent nuclear fuel at about 500 m depth in Precambrian metamorphosed rocks. The location of the site is Forsmark at the northern coast of Uppland and 122 km north of Stockholm. In geological terms Forsmark is located in the central part of the Fennoscandian...
Innehållstyp: Publikationer -
2012:58 Technical Note, Independent radionuclide transport modelling – Reproducing results for main scenarios
As part of the initial technical review of SR-Site, we applied a simplified model to approximate Swedish Nuclear Fuel and Waste Management Company (SKB) computations related to the transport of radionuclides at the planned KBS–3 repository at the Forsmark site in Sweden. The objective was to provide insights and recommendations to the Swedish Radiation Safety Authority (SSM) on potential...
Innehållstyp: Publikationer -
2012:45 Beräkning av merkostnader 2012 för avveckling och rivning av de svenska kärnkraftverken och omhändertagande av restprodukter
I föreliggande rapport presenteras Strålsäkerhetsmyndighetens beräkningar av statens förväntade framtida kostnader, de så kallade merkostnaderna. Beräkningen görs i enlighet med lagen (2006:647) om finansiella åtgärder för hanteringen av restprodukter från kärnteknisk verksamhet (finansieringslagen) och avser de förväntade...
Innehållstyp: Publikationer -
2012:55 Technical Note, Review of SKB’s Radionuclide Transport Methodology
As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to consider whether SKB’s methodology to abstract FEPs (features, events, processes), as well as site information and other data, into assessment models for radionuclide transport is appropriate and sufficient for its...
Innehållstyp: Publikationer -
2012:44 Technical Note, Review of Matrix Diffusion and related properties of intact rock in SKB’s Licence Application for a Spent Nuclear Fuel Repository in Forsmark, Sweden
This report summarizes a review of SKB’s theoretical development of matrix diffusion, its associated processes and parameters, and the data supporting calculations of matrix diffusion. In addition to diffusion, this review covers matrix porosity, the formation factor, matrix diffusivity, penetration depth, and measurement of some of these parameters with electrical methods. Sorption and the...
Innehållstyp: Publikationer -
2012:47 C-14 Long-Term Dose Assessment: Data Review, Scenario Development, and Model Comparison
BIOPROTA is an international collaboration forum which seeks to provide a transparent and traceable basis for the choices of parameter values, as well as for the wider interpretation of information used in assessments. Particular emphasis is placed on data required for the assessment of long-lived radionuclide migration and accumulation in the biosphere, and the associated radiological...
Innehållstyp: Publikationer -
2012:41 Technical Note, Hydrogeological conditions at the Forsmark site
The hydrogeological site description and groundwater models employed in support of SR-Site, in many ways, represent advances in the state of the art for crystalline bedrock where groundwater moves mainly through fractures. Advanced methods are used for representing water-conducting natural features on scales from kilometres down to a meter, as well as excavated portions of the repository...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2019:23 Participation in the European Committee for Standardization's workshop regarding civil structures
SSM perspective Background During the period 2014-2018, a CEN1 workshop (Phase 2 Prospective Group 3 civil works) have been carried out. The aim of the workshop is to provide a base founded on the French standard in order to be able to establish a possible future European standard for the design of civil structures at nuclear power plants. The workshop has identied which additional...
Innehållstyp: Publikationer -
2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...
Innehållstyp: Publikationer