Filtered generated 160 hits.
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2011:34 Evolution of hydrogen by copper in ultrapure water without dissolved oxygen
One result from this research was that the experimental difficulties of repeating Hultqvist and co-workers work are considerable and were initially underestimated. The main challenge was to obtain satisfactory tightness of all connectors involved in the experimental set-up. The problems with leakage resulted in that the research program originally planned for in this project had to be reduced...
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 -
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 -
International peer review of repository application
The Swedish Radiation Safety Authority has performed a review of SKB’s (i.e. Svensk Kärnbränslehantering AB) application for construction of a repository for spent nuclear fuel, and recommends approval of this application, as stated in our pronouncement to the Government on 23 January 2018. A peer review has also been performed by OECD’s Nuclear Energy Agency (NEA) concerning the...
Content type: Regular Pages -
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 -
2016:30 Measurement of Parameter Values for Predicting Corrosion Phenomena on Copper in Swedish HLNW Repositories
Passivity breakdown and pitting on pure copper, the assumed material for the canisters for the isolation of high-level nuclear waste in Sweden, has been studied in simulated, sulphide- and chloride containing granitic rock groundwater and the data are interpreted in terms of the Point Defect Model (PDM). The results indicated that a sulphide barrier layer forms on the copper surface, and that...
Content type: Publications -
2016:21 The effect of a glaciation on East Central Sweden: case studies on present glaciers and analyses of landform data
The Swedish Radiation Safety Authority reviews and assesses applications for geological repositories for nuclear waste. When assessing the long term safety of the repositories it is important to consider possible future developments of climate and climate-related processes. Especially the next glaciation is important for the review and assessment for the long term safety of the spent nuclear...
Content type: Publications -
2012:31 Decommissioning of the Nuclear Reactors R2 and R2-0 at Studsvik, Sweden – General Data as called for under Article 37 of the Euratom Treaty
The report describes the plans for decommissioning of the nuclear research and material test reactors R2 and R2-0, situated at the Studsvik site in Sweden. The purpose of the document is to serve as information for the European Commission, and to fulfil the requirements of Article 37 of the Euratom Treaty. According to Article 37, each Member State shall provide the Commission with such...
Content type: Publications -
2023:04 Kingdom of Sweden ARTEMIS Self-assessment Report 2023
Foreword In January 2018, the Swedish Radiation Safety Authority, SSM, submitted a request to the IAEA on behalf of the Swedish Government for international peer reviews to be conducted of the Swedish national frameworks for nuclear safety regulation (IRRS) and the safe management of spent fuel and radioactive waste (ARTEMIS). In dialogue with the IAEA, and in support of the then Swedish...
Content type: Publications