Filtered generated 403 hits.
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2014:24 Technical Note, Workshop on biosphere issues
The objective of this workshop was to bring together experts in the field of radionuclide transport in the biosphere including non-human biota and dose assessment to discuss the findings of the detailed reviews performed during the main review phase and to identify any further biosphere review issues. This report describes the outcome of the workshop organized by SSM on Biosphere Issues that...
Content type: Publications -
2012:51 Technical Note, Rock Mechanics related to long-term repository and site evolution
In general, SKB demonstrates that they have accumulated a significant set of hydraulic, mechanical and thermal data that is essential for constructing a deep geological repository. The method of data acquisition is robust using the internationally- recognized and suggested methods. The methodology of safety assessment is firmly established by applying the state-of-the-art technology and...
Content type: Publications -
2012:56 Technical Note, Biosphere Dose Assessment: Review of Dose Consequence of Radionuclides in the Uranium-238 Series Decay Chain
As part of the Swedish Radiation Safety Authority (SSM) initial phase review of the Swedish Nuclear Fuel and Waste Management Company (SKB) SR-Site safety assessment for a spent nuclear fuel repository in Sweden, this technical note documents Center for Nuclear Waste Regulatory Analyses (CNWRAÒ) review of potential effects on SKB dose calculations from radioactive elements associated with...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
2012:47 C-14 Long-Term Dose Assessment: Data Review, Scenario Development, and Model Comparison
BIOPROTA (www.bioprota.org) 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...
Content type: Publications -
2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents
In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear...
Content type: Publications -
2016:28 Fatigue fracture surface characterization and investigation
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to examine the obtained fatigue cracks with an optical microscope. Objective The present study performs a fractographical examination of the obtained fatigue cracks with the aim of determine where...
Content type: Publications