Din avgränsning ger 314 träffar.
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2019:12 Radiological risk assessment for the “Radon” type surface disposal facility in Chisinau, Moldova
Abstract The long-term conditions and potential radiological consequences of the legacy radioactive waste stored in the RADON-type disposal facility outside Chisinau is of concern for the central government authorities of the Republic of Moldova. A radiological risk assessment of “zero
Innehållstyp: Publikationer -
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,
Innehållstyp: Publikationer -
2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment
The Swedish Radiation Safety Authority (SSM) reviews and follows associated research related to the Swedish Nuclear Fuel Company’s (SKB) work with establishing a repository for spent nuclear fuel and an encapsulation facility.
Innehållstyp: Publikationer -
2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation
Innehållstyp: Publikationer -
2017:33 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – dose assessment, Kd-values, and safety analysis methodology
Main review phase
Innehållstyp: Publikationer -
2017:31 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – rock engineering and concrete barriers
Main review phase
Innehållstyp: Publikationer -
2017:30 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – consequence analysis
Main review phase
Innehållstyp: Publikationer -
2017:28 SSM’s external experts’ review of SKB’s safety assessment SR-PSU - hydrogeology, geochemistry and bentonite
Main review phase
Innehållstyp: Publikationer -
2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility
Background For final storage of spent nuclear fuel it is suggested by the Swedish nuclear fuel and waste management company (SKB) to emplace the nuclear fuel into copper canisters which are surrounded by bentonite clay at approximately 500 meters’ depth into granitic rock. After emplacement of
Innehållstyp: Publikationer -
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
Innehållstyp: Publikationer