Filtered generated 211 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 -
2021:06 Quality Assurance Review of the Swedish Nuclear Fuel and Waste Management Company’s LOT Experiment (Phase S2 and A3) at the Äspö Facility in Sweden
SSM perspective Background This report presents a quality assurance (QA) review of the work done by SKB to retrieve the S2 and A3 parcels from the Long term test of buffer material (the LOT experiment) at the Äspö Hard Rock Laboratory. Each LOT parcel comprises a heated copper tube surrounded by bentonite, with a number of copper coupons and various other test and monitoring instruments...
Content type: Publications -
2013:28 Brine intrusion by upconing for a high-level nuclear waste repository at Forsmark. Scoping calculations
SSM currently reviews a license application for a spent nuclear fuel repository that is proposed to be located at Forsmark, Sweden. The repository is to be situated at 500 m depth in the rock and copper canisters are deposited in holes excavated from the tunnel system. To protect the canisters they are surrounded by a bentonite clay buffer, which is to swell when getting in contact with...
Content type: Publications -
2014:33 Technical Note, Reproduction of SKB’s Canister Failure Calculations - What-If and ‘Residual’ Scenario to Illustrate Barrier Functions
The Swedish Nuclear Fuel and Waste Management Company (SKB) included analysis of a range of scenarios in its SR-Site report. SKB grouped these scenarios into two categories—main and residual. The main scenario included a likely scenario (corrosion failure) and a less probable scenario (seismicity-induced shear failure). The residual scenario included two unlikely scenarios—isostatic-load and...
Content type: Publications -
2015:08 Technical Note, Rheological properties of the Bentonite Buffer
Rheological properties for bentonite at high densities The properties of bentonite at high densities are extremely important and it appears as it has been to a certain extent well researched and understood, although further investigations regarding swelling of the bentonite would be welcome. What, however, seems to be missing is a comprehensive constitutive model capturing all the different...
Content type: Publications -
2012:49 Hydrogeological characteristics of sites for low- and intermediate-level waste disposal
The Forsmark area with its selected two sites and the Laxemar-Simpevarp area with its two sites are broadly similar in terms of lithology, rock ages, and tectonic histories. The two areas differ in terms of degree of deformation, and tectonic fabric. Some lithologic and tectonic differences are noticeable between the two sites in the Forsmark area and between the two sites in the...
Content type: Publications -
2014:22 Technical Note, Workshop on seismic hazard at Forsmark
This report describes the outcome of the workshop organized by SSM on seismic hazard at Forsmark that was held in Stockholm on the 4 and 5 of June, 2013. The report summarizes the issues discussed and extracts the essential viewpoints that have been expressed. It should not be considered as a comprehensive record of all the discussions at the workshop and individual statements made by...
Content type: Publications -
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.
Content type: Publications -
2015:25 Design Guide for Nuclear Civil Structures (DNB)
The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...
Content type: Publications -
2010:25 Modelling Coupled Processes in the Evolution of Repository Engineered Barrier Systems using QPAC-EBS
Currently in Sweden, the SR-Site safety assessment for a spent nuclear fuel repository is being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB). The planned SSM review of this work requires access to a sufficient modelling capability to assess the combined performance of the engineered barriers (spent fuel canister, buffer and backfill) and the natural geosphere...
Content type: Publications