Abstract

The dismantling of nuclear sites is a practice covered by Council Directive 96/29/Euratom (Basic Safety Standards).

The paper discusses the relationship between the concepts of exemption and clearance and their practical use in the overall scheme of regulatory control of practices. It introduces the concept of general clearance levels for any type of material and any possible pathway of disposal, recycling or reuse. Enveloping scenarios for general clearance and a nuclide-specific list of calculated clearance levels are presented.

A similar approach is followed by NORM materials.

For restoration of contaminated sites a common approach based on the principle of intervention has been developed.

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