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FEATURE CASE STUDY: CANDU DOSE AND RISK ASSESSMENTSInternational Safety Research frequently conducts detailed analysis of waste transfer and storage during refurbishment and normal operations for CANDU operators as part of new or ongoing licensing requirements. CANSTOR Dose EstimationsISR conducted detailed shielding studies for the transfer of nuclear waste and the operation of the radioactive waste facility for Gentilly-2 and Cernavoda power stations.ISR calculated the expected dose rates at various distances around the CANSTOR modules used to dry store spent nuclear fuel at both the Gentilly-2 in Canada and at Cernavoda in Romania. These analyses were used to estimate the collective doses associated with the construction, transfer of waste and operation of the waste facilities. Waste Transfer Dose CalculationsAs part of the proposed refurbishment of the Gentilly-2 nuclear power plant, ISR was tasked to conduct the dose rate assessments for the transport containers and the shielding casks that will be used during the transfer of the radioactive waste from the reactor building to the waste storage facility. These analyses allowed radiation protection managers to refine the work plans and the emergency plans for the transfer of these radioactive wastes.Risk Assessment in Support of DesignISR conducted the risk assessment for the proposed refurbishment of the Gentilly-2 nuclear plant. The scope of the risk assessment included the refurbishment activities, the construction and operation of on site waste storage facilities and the subsequent restart of the Gentilly-2 nuclear plant.
The risk assessment examined the risk during planned operations and also examined the risks of upset events that could generate incidents or accidents and estimated the radiological and chemical risks to humans and the environment. The risk assessment was used to refine the design criteria for seismic qualification, drop resistance, corrosion resistance, radiation damage, pressure containment and environmental verification.
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