Filtered generated 160 hits.
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2012:18 Technical Note, SR-Site Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Contribution to the Initial Review Phase
This review has focussed mainly on the modelling of the Engineered Barrier System (EBS) evolution, which includes coupled thermal, hydraulic, mechanical and chemical (THMC) processes. Additionally, the role of the EBS in the wider safety case was reviewed, including its treatment in scenarios and its representation in conceptual models since this provided the motivation for the modelling work...
Content type: Publications -
2012:34 Technical Note, Review of FEP Handling in the SR-Site Safety Assessment: Initial Review Phase
On 16th March 2011 the Swedish Nuclear Fuel and Waste Management Company, SKB, submitted applications for licences to construct a spent nuclear fuel encapsulation facility in Oskarshamn and a repository for final disposal of the encapsulated fuel in Forsmark. SKB’s applications are currently being reviewed by the Swedish Radiation Safety Authority, SSM, and the Land and Environmental Court in...
Content type: Publications -
2012:28 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes
This report consists of a Technical Note in SSM’s initial review phase of SKB’s safety analysis SR-Site. The aim of the initial review of issues concerning geochemical processes in buffer and backfill in a final repository is to make a broad illustration and review of SR-Site together with its subordinate references, as well as to identify potential needs for complementary information or...
Content type: Publications -
Radioactive waste
Radioactive waste is generated in activities where radioactive substances are used. The largest amount is generated in Swedish nuclear power plants. Some of the radioactive waste comes from other activities involving radiation, such as healthcare, research and industrial operations. Radioactive waste is generated, for example, when end-of-life fire detectors have to be disposed of, in...
Content type: Regular Pages -
2018:21 Research on Resaturation of Bentonite Buffer
Background Resaturation processes in the bentonite buffer in a KBS-3 type repository for spent nuclear fuel are complicated and are often illustrated, analysed and modelled multi-disciplinarily as coupled thermal (T), hydrological (H) and mechanical (M) processes with multi-phase flow, elastoplastic evolution in a swelling porous medium. Previous THM-modelling showed that the re-saturation...
Content type: Publications -
2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...
Content type: Publications -
2017:30 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – consequence analysis
Background The Swedish Radiation Safety Authority (SSM) received an application for the expansion of SKB's final repository for low and intermediate level waste at Forsmark (SFR) on the 19 December 2014. SSM is tasked with the review of the application and will issue a statement to the government who will decide on the matter. An important part of the application is SKB’s assessment of...
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 -
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