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Din avgränsning ger 192 träffar.

• 2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay

  SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...

  Innehållstyp: Publikationer

• 2011:22 Infiltration of dilute groundwaters and resulting groundwater compositions at repository depth

  The planned Swedish concept for final disposal of spent nuclear fuel includes copper canisters placed in deposition holes at about 500 m depth in granitic bedrock. The copper canisters will be surrounded by bentonite buffer with the objective of inhibiting groundwater flow adjacent to the canister. It has been discovered that dilute glacial melt-water may induce erosion of the buffer material.

  Innehållstyp: Publikationer

• 2011:31 Allocation of Decommissioning and Waste Liabilities

  A crucial task for the present generations is to ensure that environmental liabilities are identified sufficiently well so that it may be possible to accumulate the corresponding necessary financial assets in the Swedish Nuclear Waste Fund. Adequate funding will provide forthcoming generation’s with the financial means to decommission and dismantle older nuclear facilities that are part of...

  Innehållstyp: Publikationer

• 2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues

  The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...

  Innehållstyp: Publikationer

• 2019:16 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU

  – consequence analysis and hydrogeological aspects Main review phase...

  Innehållstyp: Publikationer

• 2014:57 Technical Note, Issues in the Corrosion of Copper in a Swedish High Level Nuclear Waste Repository: Phase III. Role of Sulphide Ion in Anodic and Cathodic Processes

  The most important findings of this research project show that: In the case when the bentonite buffer between the copper canister and the granitic rock is not damaged, we can neglect the possibility of general corrosion damage being a threat to canister integrity over a 100,000 year storage period. However, if the bentonite buffer is damaged for any reason, and does not act as an engineered...

  Innehållstyp: Publikationer

• 2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te

  Groundwater sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide concentrations which are assumed to apply throughout the long-term analysis period. The distribution is based on expert judgement in the selection of samples that are regarded as...

  Innehållstyp: Publikationer

• 2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel

  The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.

  Innehållstyp: Publikationer

• 2015:22 Technical Note, Further modelling and sensitivity study using the GEMA-Site “alternative biosphere models” and review of material from SKB’s RFI response

  Denna rapport har upprättats som en del av SSM:s huvudgranskning av SKB:s säkerhetsanalys av den långsiktiga säkerheten för KBS-3 (SR-Site), en geologisk slutförvarsanläggning, som SKB planerar uppföra i Forsmark. Granskningen tar upp de metoder som används för dosberäkningar i SR-Site, speciellt vad gäller transporter, ackumulering och...

  Innehållstyp: Publikationer

• 2015:48 Technical Note, Supplementary review of SKB’s further RFI response

  Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen (1984:3) om kärnteknisk verksamhet om uppförande, innehav och drift av ett slutförvar för använt kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta...

  Innehållstyp: Publikationer