Din avgränsning ger 269 träffar.
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2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2012:63 Technical Note, Review of Radionuclide Sorption on Bentonite and Forsmark Bedrock Material
Denna rapport granskar sorption-data för bentonit och berg vilka har använts i säkerhetsanalysen SR-Site. Det kan konstateras att härledningen av Kd-värden har gjorts på ett systematiskt sätt och att presentationen av resultat är uttömmande. Kontroller visar att härledning och överföring av resultat kan betraktas som spårbar. Det...
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 -
2012:60 Technical Note, Handling of climate related issues in the safety assessment SR-Site
The application is based on research carried out over several decades and is an impressive compilation of data and knowledge of the site of Forsmark. The sections on climate, glaciations and permafrost have developed continuously through the earlier compilations reported (e.g. the SR-97-reports). Much has been improved over the years while new question marks have occurred and some known...
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 -
2012:62 Technical Note, Review of the MARFA Code
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 review SKB’s MARFA code and consider whether the technical arguments and assumptions used for developing the code are sound, appropriate and adequate to support its use in SR-Site. This Technical Note summarises the...
Innehållstyp: Publikationer -
2011:26 The influence of temperature and fluid pressure on the fracture network evolution around deposition holes of a KBS-3V concept at Forsmark, Sweden
In preparation for the review of SKB’s license application for disposal of spent nuclear fuel, SSM is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at about 500 m depth and embedded in clay. Thus, the rock, the clay and the copper canister...
Innehållstyp: Publikationer -
2011:15 Beräkning av merkostnader 2011 för rivning av de svenska kärnkraftverken och omhändertagande av restprodukter
Denna rapport beskriver SSM:s beräkningar av framtida merkostnader inför avgiftsförslaget för 2012-2014. Beräkningen görs i enlighet med finansieringslagen och avser samtliga merkostnader fram till dess att restprodukterna från de svenska kärnkraftverken är slutligt förvarade. Enligt nuvarande beräkningar antas detta ske 2069. Uppskattningen...
Innehållstyp: Publikationer -
2011:12 Analysis of Barrier Performance: Modelling of Copper corrosion scenarios with and without buffer erosion
The purpose of this project was to develop a numerical modelling capacity to address the corrosion of the copper canister under gradually changing transport conditions caused by buffer erosion and removal of buffer mass. Due to the complexity of this task, such a model cannot be realistic in all respects, but the present effort should address the feasibility of solving numerical and...
Innehållstyp: Publikationer