Methodology to assess the radiological impact of disposals of uranium mill tailings after remediation (short term impact)

Disposal sites of uranium mill tailings are subject to remediation so as to ensure lasting protection of individuals and the environment. The options adopted for the remediation of a disposal for uranium mill tailings must be such that the current radiological and chemical impact can be reduced to levels that are as low as reasonably achievable using the best available techniques at acceptable cost. The European Directive 96/29/Euratom requires that an effective dose limit of 1 mSv/y is met, whereas the former French regulatory limit was 5 mSv/y, leading to the re-assessment of the radiological impact of the repositories based on more realistic scenarios. This study follows on from previous work undertaken by the government, COGEMA, and the Institute for Radiological Protection and Nuclear Safety (IRSN) that produced the 'Doctrine regarding the remediation of repositories for uranium mill tailings' [V-2]. On completion of this work, IRSN was asked to provide a detailed and concrete methodology for assessing a realistic radiological impact of disposals after remediation. This methodology only deals with impact assessments just after remediation. It does not tackle the questions of post remediation environment surveillance or disposal structures lifetime assessment, or long-term impact. (author)