Abstract
Worldwide there is a huge amount of radioactive waste, including disused sources, decommissioning waste, and naturally occurring radioactive material (NORM) waiting for final disposal, the so-called storage facilities. Results of safety assessment of such facilities are usually required in decision-making during design, modification, safety improvements, periodic safety reviews, and licensing activities. Quantitative safety assessment methodologies used in many areas of nuclear industry involves the evaluation of risk through the definition of scenarios, likelihoods, and consequences, for normal operation and accidents. There are many techniques that can be used in each one of these steps. For screening the accident scenarios, qualitative techniques such as failure modes and effect analysis (FMEA) are available. For a quantitative assessment of occurrence probabilities of undesired events, logical and graphical tools such as fault tree analysis (FTA) are employed. Consequence assessments involve the dose assessment in the workers and the impact of the released materials in the environment and of public exposure to radiation. This work analyzes the application of these traditional safety assessment approaches to storage facilities and how they can be applied to complement specific methodologies used in this area, such as the Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS), implemented in Safety Assessment Framework (SAFRAN) software tool, made available by International Atomic Energy Agency (IAEA).
Highlights
The 2014 regulatory position NN 8.02 [1], from the Brazilian Nuclear Energy Commission (CNEN) establishes the general criteria and basic safety conditions required for licensing of initial, intermediate and final storage facilities for low and intermediate activity level radioactive wastes
This paper provides a discussion of using different quantitative safety assessment techniques traditionally used in many areas of nuclear industry for the definition of scenarios, likelihoods, and consequences, for normal operation and accidents, and for the estimative of occurrence probabilities of undesired events
For a quantitative assessment of occurrence probabilities of undesired events, methods such as fault tree analysis (FTA), human reliability analysis (HRA), Poisson model, probabilistic seismic hazard analysis (PSHA), structural reliability analysis (SRA), and methodologies suggested by the United States Nuclear Regulatory Commission (USNRC) are employed
Summary
The 2014 regulatory position NN 8.02 [1], from the Brazilian Nuclear Energy Commission (CNEN) establishes the general criteria and basic safety conditions required for licensing of initial, intermediate and final storage facilities for low and intermediate activity level radioactive wastes. The methodologies developed on the project were implemented in a user-oriented software tool: Safety Assessment Framework – SAFRAN [2] This tool encloses all aspects of the predisposal waste management activities, including interim storage, and performs quantitative estimations for. Despite the fact that SAFRAN requires the input of the probabilities associated to each scenario, either qualitative or quantitatively, no ways of estimating these values are provided by the methodology In this context, this paper provides a discussion of using different quantitative safety assessment techniques traditionally used in many areas of nuclear industry for the definition of scenarios, likelihoods, and consequences, for normal operation and accidents, and for the estimative of occurrence probabilities of undesired events. Despite the fact that these methodologies are focused in safety assessment for interim storage for radioactive wastes, they may be applicable for other aspects of radioactive waste management
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