Din avgränsning ger 93 träffar.
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2012:59 Technical Note, Initial review phase – Dose Assessment Methodology
This report has been prepared as part of the Initial 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. In this respect the review has a natural focus upon biosphere modelling aspects of...
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 -
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 -
2012:24 Technical Note, Initial Review of SR-Site Main Report
The Swedish Radiation Safety Authority (SSM) is reviewing a license application, which has been submitted by Svensk Kärnbränslehantering AB (SKB), for a repository for the final disposal of spent nuclear fuel. SKB’s Application includes an assessment of the long-term safety of the proposed repository. The assessment is known as SR-Site. This technical note records the findings from a...
Innehållstyp: Publikationer -
2012:48 Technical Note, Use of Solubility Limits in the SR-Site Safety Assessment
In a radioactive waste disposal environment, in some potential situations (scenarios) a disposed canister containing spent fuel may be breached and the fuel may come into contact with groundwater. The concentration of a radioactive element such as uranium may rise to a level where the solution is saturated. No more of the radioactive element may dissolve and a precipitated solid may be formed.
Innehållstyp: Publikationer -
2012:45 Beräkning av merkostnader 2012 för avveckling och rivning av de svenska kärnkraftverken och omhändertagande av restprodukter
inklusive dess osäkerhet. Resultatet blev att medelvärdet i 2012 års penningvärde bedömdes till 5 050 miljoner kronor med en standardavvikelse på +/- 1 632 miljoner kronor. Penningvärden är odiskonterade. Bland ... inklusive dess osäkerhet. Resultatet blev att medelvärdet i 2012 års penningvärde bedömdes till 5 050 miljoner kronor med en standardavvikelse på +/- 1 632 miljoner kronor. Penningvärden är odiskonterade. Bland...
Innehållstyp: Publikationer -
2012:67 Technical Note, Hydrogeological modelling of the Forsmark site
A modelling study has been conducted using discrete-fracture network (DFN) models in combination with discrete-feature hydrogeological modelling methods for representation of other potentially conductive features such as the disturbed zone around repository tunnels. The principal results consist of hydraulic and transport property estimates for discrete-fracture network (DFN) models on block...
Innehållstyp: Publikationer -
2012:71 Identification of Brittle Deformation Zones and Weakness Zones
In preparation for the review of Swedish Nuclear Fuel and Waste Management Company’s (SKB) license application for disposal of spent nuclear fuel, Swedish Radiation Safety Authority (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...
Innehållstyp: Publikationer -
2012:17 Technical Note, Corrosion of copper canister
It is expected that the inflow of ground water to the deposition holes and tunnels in the Forsmark repository will be very slow. Thus, it might take some few hundred years up to thousand years before the deposition holes are filled with ground water and it might take 6000 years or more before the bentonite buffer is fully water saturated and pressurized. The copper canisters will therefore...
Innehållstyp: Publikationer -
2012:08 Deterministic Assessment of Future Costs for Dismantling (FA)
In this study a model for advanced deterministic cost calculation has been used to find a parametric value on the cost for dismantling of the FA-facility. The study gives good description of good practise to collect, test and utilise input data in a systematic way in order to make prudent cost estimates for any particular nuclear installation The Swedish Law stipulates that future expenses...
Innehållstyp: Publikationer