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Decommissioning and Management of Reactor Waste and Spent Fuel (excluding measurements)


Corrosion of copper in sulphide containing environment: the role and properties of sulphide films

Plant Life Management and Extension


Barsebäck RPV trepan studies


Study of the margin against fracture for reactor pressure vessels subjected to pressurized thermal shock transients utilizing the warm pre stressing effect: Development of general probabilistic model for cleavage fracture, numerical implementation and experimental validation

Reactor Physics


Fuel Pellet Dimensional Properties and Microstructural Fracture Modeling

Risk Analysis and Probabilistic Methods

Severe Accidents


Source Term And Timing Uncertainty in Severe accidents

Thermal Hydraulics


Thermal Hydraulics of the Suppression Pool

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Website last modified: 18 May 2022