ICRP Publication 122: Radiological Protection in Geological Disposal of Long-Lived Solid Radioactive Waste

This report updates and consolidates previous recommendations of ICRP related to solid waste disposal (Publications 46, 77, 81) (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the 2007 ICRP System of Radiological Protection described in ICRP Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a self standing document, the previous ICRP recommendations not dealt in depth in the report are still valid.

The 2007 ICRP System of Radiological Protection maintains the Commission`s three fundamental principles of radiological protection namely: justification, the application of dose limits and optimisation of protection. The Recommendations evolve from the previous process-based protection approach using practices and interventions by moving to an approach based on the exposure situation. They maintain the Commission`s current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of the optimisation of radiological protection which apply in a similar way to all exposure situations, subject to restrictions on individual doses and risks; dose and risk constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment.

This report describes the different stages in the lifetime of a geological disposal facility and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that influences the application of the protection system over the different phases in the lifetime of a disposal facility is the level of oversight or `watchful care` that is present. The level of oversight affects the capability to control the source and to avoid or reduce exposures. Three main timeframes have to be considered for the purpose of radiological protection: time of direct oversight when the disposal facility is being implemented and active control of the source by regulators is taking place; time of indirect oversight when the disposal facility is sealed and oversight is being exercised by regulators or society to provide additional assurance on behalf of the society; time of no oversight when oversight is no longer exercised in case memory is lost.

© 2013 ICRP. Published by Elsevier Ltd.

Keywords: Geological Disposal, Radioactive Waste, Protecting Future Generations

W. Weiss, C.-M. Larsson, Chr. Mckenney, J.-P. Minon, S. Mobbs, T. Schneider, H. Umeki, W. Hilden, C. Pescatore, M. Vesterlind